INDC(SEC)-46/U+R+F+SIN DC INTERNATIONAL NUCLEAR DATA ...

International Atomic Energy Agency 

INDC(SEC)-46/U+R+F+S 

I N DC 

INTERNATIONAL NUCLEAR DATA COMMITTEE 

WREKDA 75 

World Request List for Nuclear Data Measurements 

Fission Reactor Programmes 

Fusion Reactor Programmes 

Nuclear Safeguards Programmes 

June 1975 

Published on behalf of 

USA 

NEA 

IAEA 

USSR 

National Neutron Cross Section Center, Brookhaven 

Neutron Data Compilation Centre, Sac lay 

Nuclear Data Section, Vienna 

Nuclear Data Center, Obninsk 

IAEA NUCLEAR DATA SECTION, KARNTNER RING 11, A-1010 VIENNA

INDC(SEC)-46/U+R+F+S 

WRENDA 75 

World Request List for Nuclear Data 

Measurements 

Fission Reactor Programmes 

Fusion Reactor Programmes 

Nuclear Safeguards Programmes 

June 1975 

Published on behalf of 

USA 

NEA 

IAEA 

USSR 

National Neutron Gross Section Center, Brookhaven 

Neutron Data Compilation Centre, Saclay 

Nuclear Data Section, Vienna 

Nuclear Data Center, Obninsk

- iii - 

CONTENTS 

Page 

I. General Introduction to WRENDA 

A. Background and General Information I. i 

B. Editorial Policy I.v 

C. Description of Requests I.vii 

D. How to find a request in WRENDA 

1. Table of Incident Particle Sorting Order I.xiv 

2. Table of Quantity Sorting Order I.xv 

II. 

Fission Reactor Development 

A. Introduction II.i 

B. Supplementary Information from Contributors II.ii 

C. Priority Criteria II.vi 

D. List of Withdrawn Requests Il.viii 

E. Index to Fusion Request List (pink paper) Il.xiii 

F. DATA REQUEST LIST FOR FISSION REACTOR DEVELOPMENT . . . II.1 

III. 

Fusion Reactor Development 

A. Introduction Ill.i 

B. Supplementary Information from Contributors III.ii 

C. Priority Criteria ... ..... III.v 

D. Index to Fusion Request List (pink paper) Ill.vii 

E. DATA REQUEST LIST FOR FUSION REACTOR DEVELOPMENT ... III.l 

IV. 

Nuclear Safeguards and Accountability 

A. Introduction 

B. Priority Criteria IV.ii 

C. Index to the Safeguards Request List (pink paper) . . . IV.iv 

D. DATA REQUEST LIST FOR NUCLEAR SAFEGUARDS DEVELOPMENT . . IV.1

- iv - 

Appendices 

A. Country Codes A. 1 

B. Laboratory Codes B. 1 

C. Reference Codes 

List of Conference References 

C.l 

List of Journal References C.2 

List of Laboratory Reports C.3 

D. Names and Addresses of Requestors D.l

I.i 

I. General Introduction to WRENDA 

The nuclear data request lists for fission-reactors, fusionreactors 

and nuclear-safeguards development appear in Parts II, 

III and IV, respectively, of this document. Supporting information 

which is pertinent to only one of the request lists has been 

collected in sections immediately preceding the relevant request 

list. Information applicable to all the request lists appears in 

Part I. Expansions of codes used in the request lists can be found 

in the appendices at the end of the document. 

I.A. 

Background and General Information 

The use of a "request list" for communication of the 

data requirements of a developing technology to the producers 

of the required data is long standing in both the 

United States and the United Kingdom. In 1968,' the Neutron 

Data Compilation Centre at Saclay initiated publication of 

a request list for neutron data measurements from a computerized 

file, known as RENDA, on behalf of the European- 

American Nuclear Data Committee (EANDC). The list contained 

requests from the countries represented on that committee. 

In 1971, the International Nuclear Data Committee (INDC) 

recommended that the IAEA assume responsibility for publication 

of an expanded international data request list, 

which would include neutron data requests from a larger 

number of countries and international organizations. 

The data request file maintained by the Nuclear Data 

Section of the IAEA is known as WRENDA. The input to this data

I.ii 

request file is provided by officially constituted bodies in 

the Member States through the four regional Neutron Data 

Centers 1 . This issue of WRENDA is published by the IAEA on 

behalf of the four Neutron Data Centers. 

Concurrently with the transfer of responsibility for 

the neutron data request file from the NEA to the IAEA, the 

Nuclear Data Section (NDS) had developed international 

nuclear data request lists for technologies related to nuclear 

safeguards and to controlled fusion. It was expedient to 

develop the new WRENDA system to accommodate data requests 

for all applications. 

An immediate consequence of the expanded scope was that 

the new WRENDA system was designed to accommodate requests for 

data related to other nuclear processes as well as to neutroninduced 

reactions. Also concurrently with the development of 

the WRENDA system it was agreed that data requests related 

to fusion, safeguards and other applications should be handled 

through the regional data centers. 

Upon recommendation of the INDC, the international nuclear 

data request lists for fission-reactor, fusion-reactor and 

nuclear safeguards development have been published for the first 

time as a single document in this issue of WRENDA. The most 

recently preceding separate publications of the individual 

lists are identified in the following table: 

Fission Reactors INDC(SEC)-38 April 1974 

Fusion Reactors INDC(NDS)-57 December 1973 

Safeguards INDC(NDS)-50 March 1973 

1 NNCSC 

NDG'C 

NDS 

CJD 

- National Neutron Cross Section Center, Brookhaven National Laboratory, 

Upton, L.I., N.Y., USA. 

- Neutron Data Compilation Centre, Nuclear Energy Agency, Saclay, France. 

- Nuclear Data Section of the International Atomic Energy Agency, Vienna, 

Austria. 

- Centr po Jadernym Dannym, Obninsk, USSR

I. iii 

WRENDA requests for all applications are maintained in 

a single computer master-file but are associated with a particular 

application by an application code. In planning the 

present publication, it was considered that the users of WRENDA, 

who consult the publication to plan research programs, to evaluate 

research proposals and to survey data requirements, generally 

have in mind a particular application and that, therefore, 

separation of the requests according to the three applications 

mentioned above would be the most convenient form of presentation. 

Collection of the three request lists in a single 

publication should at the same time make it reasonably convenient 

to locate all requests related to the same material 

and data type by individually checking each of the lists. If 

in the future the predominant interest of the users appears 

to be in the material and data type regardless of application, 

then requests for all applications would be published in a 

single list. 

Status comments are maintained in a separate file from 

the data requests and do not bear application codes. For 

publication the requests and status comments are merged as 

described in Section I.B. When requests related to a particular 

material and data type occur in more-than-one request 

list, all status comments referring to that combination of 

material and data type are printed in each request list where 

the combination appears. 

When the same block of status comments appears in several 

request lists, some of the comments may not be relevant to any 

request in a given list, for example, because of differing energy 

ranges for the request and status information. Since only 

a small number of status blocks appear in more^-than-one request 

list, the duplication and irrelevance of some status information 

was considered justifiable in view of the convenience of reviewing 

and maintaining only a single status file rather than 

a separate one for each application.

I.iv 

The request lists are intended to serve as guides to experimentalists, 

evaluators and administrators when planning 

nuclear data measurement and evaluation programs. "When 

measurers and evaluators begin work which will provide 

data requested in this document, they are asked to inform 

the requestor(s). Information about such work should also 

be provided to the Nuclear Data Section or to a regional 

data center^ so that status comments can be kept current. 

The names of the requestors are-printed with each request, 

and their addresses are given in Appendix D. 

Future editions of WRENDA will be issued annually in 

the summer. Before each publication the national data 

committees will be asked to review their requests so that 

the lists can be kept current. 

Although major updating of the file will usually 

occur in the spring, the master-files can be updated at 

any time. Between book-publications computer listings 

of the current files can be requested from the IAEA Nuclear 

Data Section. Special sorts and selective retrievals from 

the files can also be obtained upon request. 

Comments from the users of WRENDA are encouraged so 

that the document and the special services available from 

the system can meet their needs.

I.v 

I.B. 

Editorial Policy 

During conversion from the old RENDA system to the 

new WRENDA system, an effort was made to consolidate similar 

requests from the same country in order to reduce the length 

of the WRENDA publication and to make it more easily readable. 

For example similar requests from the same country but from 

different requestors and with similar but non-identical 

comments usually were printed in WRENDA 74 as a single 

request with multiple requestors and a single identifying 

number. In general this editorial policy has been continued 

in the WRENDA 75 publication. 

If one of the multiple requestors subsequently changes 

his specifications so that his request is significantly 

different from those of the other requestors, a new identification 

number is assigned to the modified request. It has 

been tedious to trace the evolution of requests so that 

they can be correctly modified and so that the consistency 

of identification numbers can be maintained from one WRENDA 

publication to the next. 

For the future it is anticipated that new requests and 

modifications will be coded in a common format at the regional 

data centers. The modifications and identification numbers 

assigned by the regional data centers will then "be entered in 

the master files exactly as they are submitted to the NDS. 

It is hoped that any inconsistency in request numbers will 

be limited to a single year and that the cooperative WRENDA 

system will serve satisfactorily the needs of the individual 

requestors, reviewers and national data committees and will 

facilitate at the same time the production of a conveniently 

useful publication.

I.vi 

At present there seems to be a lack of consensus 

among users of WRENDA about purpose and content of the 

status comments which could be provided for each request. 

Ideally perhaps the status comments should provide a concise, 

up-to-date evaluation of the accuracy or uncertainty 

of the available data. In fact, no organization has been 

able to accept continuing responsibility of this kind for 

all requests. Alternatively the status file could provide 

only references to recently completed work and to work in 

progress although the CINDA publication provides similar 

information . An intermediate possibility would be to cite 

a recent review or evaluation related to each data request 

and to provide additional references to work completed or 

in progress after the effective date of the evaluation. 

In the present edition of WRENDA most of the status 

blocks provide only references to recently completed, continuing 

and planned work. In some status blocks a relevant 

review or evaluation is identified. For a very few blocks 

the estimated uncertainty of the available data has been 

summarized for the energy ranges specified in the associated 

requests. Comments from users about the value of the status 

information in the present edition would be particularly 

helpful in planning future editions. 

The status information in the present edition has been 

drawn from many sources. Special effort has been made to include 

information provided through national and international 

data committees. The contributions of individual experts 

who have offered their personal knowledge of particular types 

of data in concise form is gratefully acknowledged.

I.vii 

It has been assumed that general reference works such as 

BNL-325, various versions of the "chart of the nuclides" and 

CINDA are well known to the users of WRENDA. Therefore references 

to these works have been deleted from the WRENDA status file 

even though new versions of some of them may have appeared 

very recently. 

I.C. 

Description of Requests 

This edition of WRENDA contains three separate data 

request lists each of which contains only requests related 

to a particular application. Within each request list the 

form of presentation of requests is the same. 

Each request list is presented in a sort by increasing 

target charge (z) and mass (A) number, then by projectile type 

starting with the lightest (-y-rays) and sorted by increasing 

mass, and finally by reaction type. All requests for a single 

target nuclide, projectile and reaction are blocked together. 

A sample is shown on the following page. 

Each request block consists of two parts separated by 

a single line. The first part contains all the requests for one 

target-projectile-quantity combination. The second part called 

"STATUS" contains comments on the present state of knowledge 

of this data type. Where there are no status comments in the 

WRENDA file, this second part is omitted.

I.viii 

Block-heading 

The first line of each request block gives, from left 

to right, the target nuclide, the incident particle, and 

the quantity. This line of text is enclosed by a double 

line to make the beginning of each block stand out visually. 

2 

The meaning of a quantity generally conforms to CINDA 

usage with the addition of some quantities to describe 

nuclear structure data and complex reactions. A list of the 

allowed quantities appears as part of the next section. 

The target nuclide description consists of the charge number, 

the element name, and the mass number of the isotope. No 

mass number is given when the natural element is meant, 

except in the case where the natural element is monoisotopic. 

Mixtures and compounds appear at the end of the list. 

CINDA - An Index to the Literature on Microscopic Neutron Data 

published annually by the International Atomic Energy Agency

H 

fi22QZfl 15.0 MEV 10.OX 2 FR A.MICHAUDON BRC 

Q: PRODUCTION OF SC-47 (3.43 DAY). 

O: ACTIVATION DETECTOR. 

M: SUBSTANTIAL MODIFICATIONS. 

STA TUS 

ST AT US 

ANL MEADOWS* - USNDC-3 16(1972). DATA TO 6. MEV. 

AUB GHORAI+ - JNE 25 319(1971), DATA TO 6.1 MEV. 

STATUS COMMENTS

I.x 

Identification number 

The individual requests then follow in order of increasing 

identification number. This number appears on the first 

line of each request at the far left and is underlined. The 

number assigned is unique and remains associated with a 

request. When a request is withdrawn, this number is not 

assigned to another request. The first two digits of the 

identification number are the last two digits of the year 

in which the request was originated. The third digit represents 

the responsible neutron data center (1-NNCSC, 

2-NDCC, 3-NDS, 4-CJD) and the final three digits are a sequence 

number. The neutron data centers are responsible for 

assigning the identification number. 

Energy 

The next two entries on the first line of each request 

give the range of energy of the incident particle over which 

data are desired. The energy unit is given after each number. 

Because no lower case is used, we have adopted the symbol, 

MV, for milli-electron volts, thus preventing confusion with 

MEV for million electron volts. 

If an energy appears in the first field with the second 

field blank, then the requested information is required at 

only a single energy. In the case of a resonance integral, 

the single entry gives the lower energy limit for the integral. 

A lone entry in the second energy field with the first field 

blank indicates that measurement is desired for energies up to 

the specified value. This format appears most frequently for 

threshold reactions. No alphabetic energies are allowed. Thus 

thermal is given as 25.3 MV. All spectrum averages and nonstandard 

energy specifications must be explained in the requestors 

comments.

I.xi 

Accuracy 

The fourth field on the first line gives the accuracy 

required of the requested data stated in percent. Any 

accuracy requirements which cannot be stated simply must 

be given in the requestor's comments. All accuracies are 

assumed to be one standard deviation. Any other meaning must 

be explained in the comments. 

Priority 

The fifth field on the second line gives the priority 

of the requested information. Each of the three request 

lists in this publication employs a different set of priority 

criteria, which are presented in separate sections preceding 

each of the respective lists. 

Requestor 

The right hand side of the second line is used to 

identify the requestor. The first piece of information is 

a three letter code for the country originating the request. 

The codes and their explanations are given in Appendix A. 

The country code is followed by the name of the requestor. 

Mailing addresses for the requestors are given in Appendix D. 

The last piece of information is a three character code 

for the requestor's organization. These codes conform to 

the CINDA codes and are listed along with the organization 

name in Appendix B. In the case where there is more than 

one requestor for a request, then their names and organization 

codes are given on successive lines. However all requestors 

so combined must come from the same country.

I.xii 

Requestor's comments 

Comments by requestors follow below the requestors' 

names on the right hand side of the page. The comments 

are grouped into four types denoted by the characters Q, 

A, 0 and M. The group of comments designated by refers 

to further experimental specifications such as details of 

the quantity to be measured and the energy range of incident 

or secondary particles. Those denoted by an A 

refer to further details concerning accuracy or energy 

resolution required. The category 0 includes all other 

comments such as use of or justification for requested 

data. The last group of comments, designated by an M, 

contains statements about modifications which have been 

made since the previous version of WRENDA, such as "new 

request" etc. 

Status comments 

The status comments for a block of requests generally 

consist of an organization code (see Appendix B for explanations) 

followed by a name and a comment. In the 

present edition of WRENDA and for the foreseeable future 

a majority of these comments will be references to related 

, recently completed experiments or to experiments 

underway. In some cases, general status comments as to 

various discrepancies or attained accuracies will appear. 

It is hoped that more comments of this type will appear in 

the future. 

All references to publications use CINDA-type codes. 

These codes and their expanded formsare given in Appendix C. 

The name given at the beginning of a comment is either the 

author or first author of a publication or the source of the 

general comment.

I.xiii 

I.D. 

How to find a request in WRENDA 

In this publication WRENDA requests have been collected 

in three separate lists according to application. The request 

list for fission-reactor development appears in Part II, the 

list for fusion research and reactor development in Part III, 

and the list for nuclear safeguards development in Part IV. 

As is discussed in the previous section, within each list 

all data requests for a single target nucleus, projectile, 

and reaction quantity are blocked together. These blocks 

are sorted by target - projectile - reaction in that order. 

The target nuclei are in increasing order of Z and, 

within Z, A. Elements which are iso topic mixtures appear 

before individual isotopes. Monoisotopic elements appear 

at their natural position in order of increasing A. Following 

the request blocks of highest Z are requests in which the 

target is lumped fission products and, finally, requests in 

which the target is an alloy or chemical compound. 

Immediately preceding each of the request lists is 

an index printed on coloured paper. The index gives the 

number of the page in the following request list on which 

the first block for any target nucleus (Z, A) appears. 

In this section are two additional tables for assistance 

in locating requests. The first table gives the projectileparticle 

sort order, and the second table gives the reaction 

quantity sort order.

I.xiv 

Table I 

Incident Particle Sorting Order 

1 No incident particle (e.g. level structure) 

2 Photon 

3 Neutron 

4 Proton 

5 Deuteron 

6 Triton 

7 Helium-3 

8 Alpha 

9 Lithiuro-6

I.XV 

Table II (page l) 

QUANTITY SORT ORDER 

LEVEL DENSITY PARAMETERS 

DISCRETE LEVEL STRUCTURE (ENERGY, SPIN, PARITY) 

HALF LIFE 

FISSION HALF LIFE 

TOTAL CROSS SECTION 

ELASTIC CROSS SECTION 

DIFFERENTIAL ELASTIC CROSS SECTION 

INELASTIC CROSS SECTION 

ANGULAR DIFFERENTIAL INELASTIC CROSS SECTION 

ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

THERMAL SCATTERING LA* 

TOTAL SCATTERING CROSS SECTION 

DIFFERENTIAL TOTAL SCATTERING CROSS SECTION 

NON-ELASTIC CROSS SECTION 

ABSORPTION CROSS SECTION 

CAPTURE CROSS SECTION 

TNERGY DIFFERENTIAL CAPTURE CROSS SECTION 

CAPTURE GAM PA RAY SPECTRUM 

DELAYED CAPTURE GAMMA RAY SPECTRUM 

PHOTON PRODUCTIGN CROSS SECTION IN INELASTIC SCATO 

TOTAL PHOTON PRODUCTION CROSS SECTION 

TOTAL GAMMA RAY YIELD 

X.N 

X,N NEUTRON SPECTRA 

X ,2N 

X,2N NEUTRON SPECTRA 

X.3N 

NEUTRON EMI SSICN CROSS SECTION 

TOTAL NEUTRON YIELD 

DELAYED NEUTRON YIELD 

ENERGY DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION 

DOUBLE DIFFERENTIAL NEUT RON-EMISSION CROSS SECTION 

X ,P 

X,P DELAYED NEUTRON YIELD 

X,NF 

X,2 F 

TOTAL PROTON PRODUCTION CROSS SECTION 

X ,0 

X , ND 

X ,T 

X ,NT 

X ,HELIUM—3 

X, ALPHA 

X,NALPHA 

X,N3ALPHA

I.xvi 

Table II (page 2) 

TOTAL ALPHA PRODUCTION CROSS SECTION 

FISSION CROSS SECTION 

SECOND CHANCE FISSION CROSS SECTION 

CAPTURE TO FISSION RATIO (ALPHA) 

NEUTRONS EMITTED PER NEUTRON ABSORPTION (ETA) 

NEUTRONS EMITTED PER NON-ELASTIC PROCESS 

NEUTRONS EMITTED PER FISSION (NU BAR) 

DELAYED NEUTRONS EMITTED PER FISSION 

PROMPT NEUTRONS EMITTED PER FISSION 

INFORMATION ON NEUTRONS FROM A FISSION FRAGMENT 

ENERGY SPECTRUM OF FISSION NEUTRONS 

ENERGY SPECTRUM OF DELAYED FISSION NEUTRONS 

SPECTRUM OF PROMPT GAMMA RAYS EMITTED IN FISSION 

SPECTRUM OF GAMMA RAYS EMITTED IN FISSION 

DELAYED GAMMA SPECTRUM FROM FISSION PRODUCTS 

FISSION PRODUCT MASS YIELD SPECTRUM 

INFORMATION ON KINETICS OF FISSION FRAGMENTS 

RESONANCE PARAMETERS 

ABSORPTION RESONANCE INTEGRAL 

CAPTURE RESONANCE INTEGRAL 

FISSION RESONANCE INTEGRAL

I. i 

II. Fission Reactor Development 

II. A. 

Introduction 

The fission list contains over 1200 requests for improved 

nuclear data needed in support of the fission-reactor development 

programs of 21 Member States of the IAEA and one 

International Organization. The requests from Belgium, 

Canada, France, India, Italy, Japan, the Soviet Union, 

Sweden, Switzerland, Turkey, the United Kingdom and the 

United States have been reviewed and updated since the last 

publication of the WRENDA fission list (lNDC(SEC)-38, 

April 1974). 

In WRENDA 74 it was implied that the next edition of 

the data request list for fission reactors would contain 

both a list of satisfied requests and a list of withdrawn 

requests. While many requests which appeared in WRENDA 74 

have been withdrawn from the present edition, only a very 

few were explicitely marked "satisfied". From examination 

of the other withdrawn requests it was concluded that some 

of them may have been withdrawn because they were, in fact, 

partially or totally satisfied. Because of apparently inconsistent 

distinction between withdrawn and satisfied 

requests, the present edition of the data request list for 

fission-reactor applications is accompanied only by a list of 

withdrawn requests, which should be considered to include 

also satisfied requests.

I. ii 

II. B. 

Supplementary information from contributors 

[ Requestors and national data committees 

sometimes supply supplementary information about 

the requests for which they are responsible. 

The remarks which follow were received from 

the USSR.] 

General comments to the Soviet Requests 

L.N. Usachev's requests 

Together all the requests make a unique system of 

requirements for the accuracy of evaluated nuclear data 

which would assure calculation of K^^, and breeding ratio (BR) 

of a fast plutonium breeder with accuracies of lfo ajid 2$ 

respectively. 

Priorities 

Accuracy requirements designated 2nd priority would 

assure the necessary calculational accuracy on the basis 

only of microscopic data without the use of data from 

integral experiments. 

Accuracy requirements of designated 1st priority are 

less stringent because use would be made of evaluated results 

from integral experiments, which are available at the Nuclear 

Data Centre in Obninsk. 

Meaning of uncertainty 

Uncertainty (or accuracy) is characterized by one 

standard deviation.

Il.iii 

Uncertainty of a point is. supposed to be represented as 

a sum of components with different correlative properties. 

Accuracy specifications are for those components of the uncertainty 

which determine the accuracy of the integral under 

the curve in the partial energy interval mentioned in each 

request. 

In requests for measurements the use of standards - v 

of 2 5 2 Cf, the 10 B (n, a) cross section (below 100 keV) and 

the (n,f) cross section (above 100 keV) - is assumed. 

In all requests except those for standards, the accuracy 

specifications refer to measurements relative to standards, 

and the accuracies required of the standards are specified 

separately. 

The algorithm used to derive these 

described in the following papers! 

requirements is 

L.N. Usachev and Yu.G. Bobkov, "Planning of an optimum set of 

microscopic experiments and evaluations to obtain a given 

accuracy in reactor parameter calculations'* Evaluation of 

Nuclear Data, (Proc. Panel, Vienna, 1971), Report IAEA-153, 

IAEA, Vienna, 1973 (in Russian). English translation: 

INDC(CCP)-19 (1972). 

L.N. Usachev, V.N. Manokhin and Yu. G. Bobkov, "The accuracy 

of nuclear data and its influence on fast reactor development", 

Nuclear Data in Science and Technology, (Proc. Symp., Paris, 1973) 

IAEA, Vienna, 1973, Vol. 1, p. 129 (in Russian).

I. iv 

3. Yu.G. Bobkov, L.T. Pyatnitskaya and L.N. Usachev, "Planning 

of experiments and evaluations on neutron data for reactors " 

The Metrology of Neutron Radiation in Reactors and Accelerators. 

(Proc. Gonf., Moscow, 1974), Report FEI-^27 (1974) (in Russian). 

English translation to be published as INDC(CCP) document. 

4. L.N. Usachev, "Unique definition of nuclear data accuracy" 

7th INDC Meeting, Lucas Heights, 1974, Proceedings in preparation 

(in English). Report FBI-537 (1974) (in Russian). 

M.N. Nikolaev's requests 

Basic demands for accuracy of 

are 1 and 1.6 percent, respectively. 

and BR prediction 

The requests are formulated for the totality of microscopic 

data without taking into account the results of 

integral experiments. Therefore, these requests are, as a 

rule, of the second priority. 

The comparatively less demandng accuracies specified in 

this set of requests are stipulated by an assumption about 

the sense of uncertainties which differs from the assumption 

used in Usachev's requests. In this set of requests complete 

correlation of uncertainties within each group in the ABBN 

26-group set and full statistical independence of uncertainties 

of neighbouring groups is supposed. 

Correlation of uncertainties for different isotopes, 

cross sections and v values is taken into account by assuming 

as standards the U-235 fission cross section and v of Cf-2^2.

I. xxvi 

The author of the requests considers that these conditions 

would exist for instance," when on each adjacent lethargy 

interval 0.5-1 there would fall, on the average, one experiment 

carried out by an independent method with the requested, 

guaranteed accuracy. 

The algorithm of request formulation and substantiation 

of basic requirements for and BR are described in paper 

by S.M. Zaritsky, M.N. Nikolaev, M.F. Troyanov, "Nuclear 

Data Requirements for Calculation of Fast Reactors", 

Report INDC(CCP)-17, IAEA, Vienna, 1972. 

Conclusion 

The two sets of requirements presented here emphasize 

the importance of precise understanding of accuracy 

specifications.

I. vi 

II.C. 

Priority Criteria 

Three priorities, noted 1, 2 and 3 (l "being the highest), 

can be attributed to the requests. The priorities are defined 

as follows: 

* Priority 1 * 

Nuclear data which satisfy the criteria of Priority 2 

and which have been selected for maximum practicable 

attention, taking into account the urgency of nuclear 

energy programme requirements. 

For example, the European American Committee for 

Reactor Physics assigns its highest priorities for reactor 

measurements as follows: 

"The highest priority should be given to requests 

for nuclear data for reactors to be built in the near 

future if: 

a. These data are still necessary to predict the 

different reactor properties after all information from 

integral experiments and operating reactors has been used; 

or 

b. information on an important reactor parameter is 

in principle attainable through mathematical calculation 

from nuclear data only; or 

c. these data are needed for materials required in 

reactor physics measurements."

Il.vii 


Nuclear data which will be required during the next 

few years in the applied nuclear energy programme 

(e.g. the design of a reactor or fuel processing plant; 

data needed for optimum use of reactor fuel and construction 

materials such as neutron moderators, absorbers and radiation 

shields; space application and biomedical studies; data 

required for better understanding of some significant aspect 

of reactor behaviour). 


Nuclear data of more general interest and data 

required to fill out the body of information needed for 

nuclear technology.

II.D. LIST CF WITHDRAWN REQUESTS 

691004 USA 2 HELIUM 3 NEUTRON N , P 

691006 USA 3 LITHIUM NEUTRON TOTAL PHO T ON PRODUCTION CROSS SECTION 

691007 USA 3 LI THI LM NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

70 1 C 01 USA 3 LITI-IUM 6 NEUTRON N,ALPHA 

621 C-01 USA 4 BERYLLIIf 9 NEUTRON DIFFERENTIAL ELASTIC CROSS SEC T I ON 

691C14 USA 4 BERTLLHK 9 NEUTRON CAPTURE CROSS SECTION 

68 2002 JAP 4 8ERYLLILC 9 NEUTRON N, 2N 

682003 JAP 5 BORCN 1C NEUTRON ABSORPTION CROSS SECTION 

701003 USA 5 BOFCN 1C NEUTRON N.ALPHA 

6210 03 USA 6 CA RBON NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

621004 USA 6 CARBON NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

6610 02 USA 6 CARBON NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

742025 FR 6 CARBON NEUTRCN DIFFERENTIAL EL AS T IC CROSS SECTION 

742026 FR 6 CARBON NEUTRON DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

692014 - R 6 CARBON NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691115 USA 8 OXYGEN NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

6911 ; 6 USA 8 OXYGEN NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

651120 USA 8 OXYGEN NEUTRON NEUTRON EMISSION CROSS : SECTION 

721029 USA 8 OXYGEN ALPHA ALPHA.N 

682006 JAP e OXYGEN 16 NEUTRON N.ALPHA 

6910^0 USA 9 FL LOR INE 19 NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

691041 USA 9 FLUCRINE 19 NEUTRON NEUTRON EMISSION CROSS : SECT ION 

691042 USA S FLUCRINE 19 NEUTRON N.ALPHA 

691043 USA 11 SODIUM 23 NEUTRON TOTAL CROSS SECTION 

591C47 USA 11 SOD I UP 23 NEUTRON ABSORPTION CROSS SECTION 

6950 07 SA

II.D. LIST OF HITHDRAWN REQUESTS (continued) 

721042 USA 26 I RCN NEUTRON RESONANCE PARAMETERS 

742034 FR 26 IRON 56 NEUTRON N, 2N 

66 1023 USA 27 COBALT 58 DISCRETE LEVEL STRUCTURE (ENERGY. SPIN. DARITY) 

691205 USA 27 COBALT 59 NEUTRCN CAPTURE CROSS SECTION 

691107 USA 27 COBALT 59 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691108 USA 27 COBALT 59 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

692114 FR 27 COBALT 59 NEUTRCN N, 2N 

621018 USA 27 COBALT 59 NEUTRON RESONANCE PARAMETERS 

721050 USA 28 NICKEL NEUTRON ABSORPTION CROSS SECTION 

661027 USA 28 NICKEL NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

69 1124 USA 28 NICKEL NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691125 USA 28 NICKEL NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

70 2011 JAP 28 NICKEL 58 NEUTRON CAPTURE CROSS SECTION 

693017 IND 28 NICKEL 58 NEUTRON N,ALPHA 

702012 JAP 28 NICKEL 60 NEUTRON CAPTURE CROSS SECTION 

691131 USA 29 COPPER NEUTRON CAPTURE CROSS SECTION 

691129 USA 29 COPPER NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691130 USA 29 COPPER NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691134 USA 29 COPPER NEUTRON N. 2N 

69 1138 USA 30 ZINC NEUTRON CAPTURE CROSS SECTION 

691135 USA 30 ZI NC NEUTRON CAPTURE GAMMA RAY SPECTRUM 

691136 USA 30 ZINC NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691137 USA 30 ZINC NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

721057 USA 30 ZINC NEUTRON N, 2N 

742036 FR 31 GALL IUM NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

742037 FR 31 GALL IvM NEUTRON DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

742039 FR 31 GALLIUM NEUTRON CAPTURE CROSS SECTION 

692148 FR 37 RUBIDIUM 85 NEUTRON CAPTURE CROSS SECTION 

692149 FR 39 YTTRIUM 89 NEUTRON N, 2N 

691144 USA 40 ZIRCONILM NEUTRON CAPTURE GAMMA RAY SPECTRUM 

69 1 1 45 USA 40 ZIRCONIUM NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691146 USA 40 ZIRCONIUM NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

6911 41 USA 40 ZIRCONIUM NEUTRON NEUTRON EMISSION CROSS SECTION 

671007 USA 40 ZIRCONILM 90 NEUTRON NEUTRON EMISSION CROSS SECTION 

721069 USA 40 ZIRCONIUM 96 NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

691164 USA 40 ZIRCONILM 96 NEUTRON CAPTURE CROSS SECTION 

691165 USA 41 NIOBIUM 93 NEUTRON INELASTIC CROSS SECTION 

691297 USA 41 NIOBIUM 93 NEUTRON CAPTURE GAMMA RAY SPECTRUM 

691167 USA 41 NIOBIUM 93 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691168 USA 41 NIOBIUM 93 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

701037 USA 41 NIOBIUM 93 NEUTRON N. 2N 

691166 USA 41 NICBIUM 93 NEUTRON NEUTRON EMISSION CROSS SECTION 

6911 72 USA 42 MOLYBDENUM NEUTRON CAPTURE GAMMA RAY SPECTRUM 

691173 USA 42 MOLYBDENUM NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691174 USA 42 MOLYBDENUM NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691224 USA 42 MOLYBDENUM NEUTRON NEUTRON EMISSION CROSS SECTION 

692161 FR 42 MOLYBDENUM 92 NEUTRON N,ALPHA 

682024 UK 43 TECHNETIUM 99 NEUTRON CAPTURE CROSS SECTION 

6921 68 JAP 43 TECHNETIUM 99 NEUTRON CAPTURE CROSS SECTION 

692171 JAP 44 RUTHENIUM 100 NEUTRON . CAPTURE CROSS SECTION 

682026 UK 44 RUTHENIUM 101 NEUTRON CAPTURE CROSS SECTION 

692179 SWT 45 RHODIUM 103 NEUTRON PHOTON PRODUCTION CROSS SECTION IN INELASTIC SCATe 

742041 FR 45 RHODIUM 103 NEUTRON N, 2N 

6921 81 JAP 45 RHODIUM 105 NEUTRON CAPTURE CROSS SECTION 

II.ix

II.D. LIST OF WITHDRAWN RECUESTS (continued) 

692478 ITY 46 PALLADIUM 109 NEUTRON RESONANCE PARAMETERS 

692191 SWT 48 CADMIUM NEUTRON ABSORPTION CROSS SECTION 

692198 UK 54 XENON 131 NEUTRON ABSORPTION CROSS SECTION 

68 20 32 UK 54 XENCN 131 NEUTRON ABSORPTION RESONANCE INTEGRAL 

692202 JAP 54 XENON 133 NEUTRON CAPTURE CROSS SECTION 

692206 JAP 55 CESIUM 134 NEUTRON CAPTURE CROSS SECTION 

69 2217 JAP 59 PRASEODYMIUM 143 NEUTRON CAPTURE CROSS SECTION 

702018 JAP 60 NEODYMIUM 143 NEUTRON CAPTURE CROSS SECTION 

682033 UK 61 PRCMETHUM 147 NEUTRON ABSORPTION CROSS SECTION 

68 20 34 UK 61 PRCMETHIUM 147 NEUTRON CAPTURE CROSS SECTION 

70 2019 JAP 61 PRCMEThlUM 147 NEUTRON CAPTURE CROSS SECTION 

692226 UK 61 PRCMETHILM 147 NEUTRON ABSORPTION RESONANCE INTEGRAL 

692229 JAP 61 PRCMEThlUM 148 NEUTRON CAPTURE CROSS SECTION 

692245 JAP 62 SAMARIUM 150 NEUTRON CAPTURE CROSS SECTION 

68 20 35 UK 62 SAMARIUM 151 NEUTRON CAPTURE CROSS SECTION 

692250 JAP 62 SAMARIUM 152 NEUTRON CAPTURE CROSS SECTION 

702020 JAP 62 SAMARIUM 152 NEUTRON N.P 

661060 USA 63 EUROPIUM NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

671063 USA 63 EUROPIUM 151 NEUTRON CAPTURE CROSS SECTION 

691179 USA 63 EUROPIUM 151 NEUTRON CAPTURE CROSS SECTION 

691178 USA 63 EUROPIUM 151 NEUTRON N,2N 

692267 JAP 63 E UROPIUM 154 NEUTRON CAPTURE CROSS SECTION 

742044 FR 64 GADOLINIUM NEUTRON CAPTURE CROSS SECTION 

692270 I TV 64 GADOLI MUM NEUTRON RESONANCE PARAMETERS 

70 20 21 JAP 64 GADOLINIUM 158 NEUTRON N.P 

6922 84 SWT 66 DYSPROSIUM 164 NEUTRON CAPTURE CROSS SECTION 

692285 ITY 67 HGLMIUM 165 NEUTRON RESONANCE PARAMETERS 

70 2022 JAP 68 ERBIUM 166 NEUTRON N.F 

702023 JAP 68 EREIUM 168 NEUTRON N. F 

671C75 USA 69 THULIUM 169 NEUTRON CAPTURE CROSS SECTION 

692288 FR 69 THLUIUM 169 NEUTRON N, 2N 

692287 I TY 69 THULIUM 169 NEUTRON RESONANCE PARAMETERS 

671076 USA 69 THULIUM 170 NEUTRON CAPTURE CROSS SECTION 

671078 USA 69 THULIUM 171 NEUTRON CAPTURE CROSS SECTION 

702024 JAP 70 YTTERBIUM 174 NEUTRON N.P 

621023 USA 72 HAFNILM NEUTRON CAPTURE CROSS SECTION 

691393 USA 73 TANTALUM 181 NEUTRON CAPTURE CROSS SECTION 

691395 USA 73 TANTALUM 181 NEUTRON CAPTURE CROSS SECTION 

691209 USA 73 TANTALUM 181 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691210 USA 73 TANTALUM 181 NEUTRON TOTAL PHOTON PRODUCTICN CROSS SECTION 

691191 USA 73 TANTALUM 181 NEUTRON NEUTRON EMISSION CROSS SECTION 

691198 USA 74 TUNGSTEN NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691199 USA 74 TUNGSTEN NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

742048 FR 74 TUNGSTEN NEUTRON N • 2N 

691196 USA 74 TUNGSTEN NEUTRON NEUTRON EMISSION CROSS SECTION 

682C40 JAP 79 GOLD 197 NEUTRON CAPTURE CROSS SECTION 

7C10 25 USA 79 GOLD 157 NEUTRON CAPTURE CROSS SECTION 

692315 FR 79 GOLD 157 NEUTRON N. 2N 

682C47 JAP 82 LEAD NEUTRON TOTAL CROSS SECTION 

69 1212 USA 82 LEAD NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

691213 USA 82 LEAD NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

682048 JAP 88 RADIUM 226 NEUTRON CAPTURE CROSS SECTION 

682049 JAP 90 THORIUM 232 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

691398 USA 9C THORIUM 232 NEUTRON ABSORPTION CROSS SECTION 

II.X

II.D. LIST OF WITHDRAWN FIECUESTS (continued) 

671 084 USA 90 THORIUM 232 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

742065 FR 92 URANIUM 232 NEUTRON CAPTURE CROSS SECTION 

7420 64 FR 92 URANIUM 232 NEUTRON FISSION CROSS SECTION 

692351 FR 92 URANIUM 233 NEUTRCN CAPTURE CROSS SECTION 

671094 USA 92 URANIUM 233 NEUTRON CAPTURE GAMMA RAY SPECTRUM 

67* C 87 USA 92 URANIUM 233 NEUTRON N, 2N 

693046 INO 92 URANIUM 233 NEUTRON FISSION CROSS SECTION 

742066 FR 92 URANIUM 233 NEUTRON FISSION CROSS SECTION 

621046 USA 92 URANIUM 233 NEUTRON PROMPT NEUTRONS EMITTED PER FISSION 

693048 IND 92 URANIUM 233 NEUTRON INFORMATION ON NEUTRONS FROM A FISSION FRAGMENT 


692354 FR 92 URANIUM 234 NEUTRON FISSION CROSS SECTION 

62 1 C4 7 USA 92 URANIUM 234 NEUTRON PROMPT NEUTRONS EMITTED PER FISSION 

661042 USA 92 URANIUM 235 NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

691240 USA 92 URANIUM 235 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SE CTION 

691242 USA 92 URANIUM 235 NEUTRON FISSION CROSS SECTION 

693055 SAF 92 URANIUM 235 NEUTRON FISSION CROSS SECTION 

693C56 IND 92 URANIUM 235 NEUTRON FISSION CROSS SECTION 

70 2C27 JAP 92 URANIUM 235 NEUTRON FISSION CROSS SECTION 

71 2056 JAP 92 URANIUM 235 NEUTRON FISSION CROSS SECTION 

6912 52 USA 92 URANIUM 235 NEUTRON CAPTURE TO FISSION RATIO (ALPHA) 

71 4C10 CCP 92 URANIUM 235 NEUTRON NEUTRONS EMITTED PER FISSION (NU 6AR) 

6 912 59 USA 92 URANILM 235 NEUTRON DELAYED N5UTRONS EMITTED PES FISSION 

71 2061 JAP 92 URANILM 235 NEUTRCN DELAYED NEUTRONS EMITTED PER FISSION 

693058 IND 92 URANIUM 235 NEUTRON INFORMATION ON NEUTRONS FROM A FISSION FRAGMENT 

621048 USA 92 URANIUM 236 NEUTRON PROMPT NEUTRONS EMITTED PER FISSION 

7C 20 30 JAP 92 URANIUM 238 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

6914 72 USA 92 URANIUM 238 NEUTRON CAPTURE CROSS SECTION 

691816 CAN 92 URANIUM 238 NEUTRON CAPTURE CROSS SECTION 

692396 FR 92 URANIUM 238 NEUTRON N. 2N 

742085 FR 92 URANIUM 238 NEUTRON N I 3N 

693064 SAF 92 URANIUM 238 NEUTRON FISSION CROSS SECTION 

712068 JAP 92 URANIUM 238 NEUTRON FISSION CROSS SECTION 

71 2070 JAP 92 URANIUM 238 NEUTRCN DELAYED NEUTRONS EMITTED PER FISSION 


671114 USA 93 NEPTUNIUM 237 NEUTRON CAPTURE CROSS SECTION 


70 10 36 USA 93 NEPTUNIUM 237 NEUTRON N,2N 

67 11 13 USA 93 NEPTUNIUM 237 NEUTRON FISSION CROSS SECTION 

71 2.0 72 JAP 93 NEPTUNIUM 237 NEUTRON FISSION CROSS SECTION 


671120 USA 94 PLUTONIUM 238 NEUTRON CAPTURE CROSS SECTION 

691301 USA 94 PLUTONIUM 238 NEUTRON CAPTURE CROSS SECTION 

721083 USA 94 PLUTONIUM 238 NEUTRON FISSION CROSS SECTION 

6210 52 USA 94 PLLTONILM 238 NEUTRON PROMPT NEUTRONS EMITTED PER FISSION 

671121 USA 94 PLLTONILM 239 NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

691 81 7 CAN 94 PL L TON IUM 239 NEUTRON CAPTURE CROSS SECTION 

691818 CAN 94 PLUTONIUM 239 NEUTRON CAPTURE CROSS SECTION 

693079 IND 94 PLLTONIUM 239 NEUTRON CAPTURE CROSS SECTION 

701039 USA 94 PLUTONIUM 239 NEUTRON NEUTRON EMISSION CROSS SECTION 

682069 JAP 94 PLLTONIUM 239 NEUTRON FISSION CROSS SECTION 

691819 CAN 94 PLUTONIUM 239 NEUTRON FISSION CROSS SECTION 

69 30 71 IND 94 PLUTONIUM 239 NEUTRON FISSION CROSS SECTION 

693073 SAF 94 PLLTONIUM 239 NEUTRON CAPTURE TO FISSION RATIO (ALPHA) 

II.xi

II.D. LIST CF WITHDRAWN RECLESTS (continued) 

691820 CAN 94 PLLTONIUM 239 NEUTRON NEUTRONS EMITTED PER NEUTRON ABSORPTION (ETA) 

714027 CCP 94 PLLTONILM 239 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR) 

71 20 84 JAP 94 PLUTONIUM 239 NEUTRON DELAYED NEUTRONS EMITTED PLR FISSION 

693075 IND 94 PLLTONIUM 239 NEUTRON INFORMATION ON NEUTRONS FROM A FISSION FRAGMENT 

71 2085 JAP 94 PLLTONIUM 240 NEUTRON TOTAL CROSS SECTION 

682070 JAP 94 PLLTONIUM 240 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

712088 JAP 94 PLLTONIUM 240 NEUTRON CAPTURE CROSS SECTION 

71 2089 JAP 94 PLLTONIUM 240 NEUTRON CAPTURE CROSS SECTION 

712086 JAP 94 PLLTONILM 24C NEUTRON FISSION CROSS SECTION 

71 2C90 JAP 94 PLLTONIUM 240 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION 

71 2091 JAP 94 PLL TON IUM 241 NEUTRON TOTAL CROSS SECTION 

71 2098 JAP 94 PLLTONIUM 241 NEUTRON CAPTURE CROSS SECTION 

691821 CAN 54 PLLTONILM 241 NEUTRON FISSION CROSS SECTION 

691822 CAN 94 PLLTONIUM 241 NEUTRON NEUTRONS EMITTED PER NEUTRON ABSORPTION ( ETA) 

691823 CAN 94 PLLTONIUM 241 NEUTRON NEUTRONS EMITTED PER NEUTRON ABSORPTION (ETA) 

671199 USA 94 PLLTONILM 242 NEUTRON CAPTURE CROSS SECTION 

67 11 34 USA 94 PLLTONILM 242 NEUTRON N.P 

621055 USA 54 PLLTONILM 242 NEUTRON PROMPT NEUTRONS EMITTED PER FISSION 

682073 JAP 95 AMEFTLCIUM 241 NEUTRON CAPTURE CROSS SECTION 

671138 USA 95 AMERICIUM 243 NEUTRON TOTAL CROSS SECTION 

671140 USA 96 CURIUM 24 3 NEUTRON TOTAL CROSS SECTION 

691343 USA 96 CURIUM 243 NEUTRON CAPTURE CROSS SECTION 

67 11 41 USA 96 CURIUM 243 NEUTRON FISSION CROSS SECTION 

691342 USA 96 CURIUM 243 NEUTRON FISSION CROSS SECTION 



691349 USA 96 CURIUM 246 NEUTRON FISSION CROSS SECTION 

6913 51 USA 96 CURIUM 247 NEUTRON FISSION CROSS SECTION 

671150 USA 96 CURIUM £48 NEUTRON TOTAL CROSS SECTION 

69 1 3 53 USA 96 CURIUM 248 NEUTRON CAPTURE CROSS SECTION 


6913 55 USA 98 CALIFORNIUM 249 NEUTRON FISSION CROSS SECTION 

691356 USA 98 CALIFORNIUM 250 NEUTRON FISSION CROSS SECTION 

691824 CAN 98 CALIFORNIUM 252 SPONTANEOUS NEUTRONS EMITTED PER FISSION (NU BAR) 

714034 CCP 98 CALIFORNIUM 252 SPONTANEOUS NEUTRONS EMITTED PER FISSION (NU BAR) 

721104 USA 98 CALIFOFNIUM 252 SPONTANEOUS ENERGY SPECTRUM OF FISSION NE :UTRONS 

691358 USA 98 CALIFORNIUM 252 NEUTRON FISSION CROSS SECTION 

6711 56 USA 98 CALIFORNIUM 253 NEUTRON CAPTURE CROSS SECTION 

6913 60 USA 99 EINSTEINIUM 253 NEUTRON FISSION CROSS SECTION 

671157 USA 99 EINSTEINIUM 254 NEUTRON CAPTURE TO FISSION RATIO (ALPHA) 

691361 USA 100 FERMI CM 255 NEUTRON FISSION CROSS SECTION 

691362 USA 100 FERMILM 257 NEUTRON FISSION CROSS SECTION 

Il.xii

II.E. 

Index to Fission Request List 

page 

1 HYDROGEN 1 oooooooooocooec IIo 1 

; HYDROGEN 2 oocooooooeooooo IIo 1 

2 HELIUM 3 OCOOOQOOCOOOOOO IIo 1 

3 LITH I UM 6 O O O C C C 3 5 C 9 0 0 0 0 0 lie 1 

3 L I THI UM 7 ooooooooooooooo IIo 2 

4 BERYLLIUM 5 I O O O C C SOOCCOOOC lie 2 

5 BORON oooooooooocoooo IIo 

5 BORON 10 OOOOCOOOOCCCOOO Ho 

6 CARBON OOOOOOOOOOOOOOO IIo 4 

e CARBON 12 oooooooocccocoo IIo 4 

7 NITROGEN oooooooooocoooo IIo 4 

7 NITROGEN 14 OOOOOOOOOOCOOOC IIo 4 

e OXYGEN ooooooooooooooo IIo 5 

8 OXYGEN 16 oooooooooooooco IIo 6 

e 3XYGEN 17 OOOCOOOOOOOOQOO H o 6 

8 OXYGEN 18 ooooooooooocooo lie 6 

5 FLUORINE cococoooooooooo lie 6 

5 =LLORINE 1? ooooooooocoocoo Ilo 6 

11 SODIUM 23 ooeooooceccocoo IIo 6 

1 3 ALUMINUM 27 ooooooooooooooo IIo 9 

15 PHOSPHORUS 31 oooooooooocoooc IIo 9 

i e SULFUR oooooooooooocoo IIo 9 

le SLLFUR 32 oooooooooooocoo IIo 10 

1 7 CHLORINE occoocoooocoooo IIo 10 

1 7 CHLORINE 36 oooooooocoooooo IIo 10 

1 E ARGON 40 ocoooooocoooooo IIo 10 

IS POTASSIUM 41 ooooooooooooooo IIo 10 

2C CALCIUM oeoocoooooooooo IIo 10 

21 SCANDIUM 45 ooooooooooooooo IIo 10 

22 TITANIUM oocoooooooooooo IIo 11 

22 TITANIUM 46 ooooooooooooooo IIo 11 

22 TITANIUM 4 7 ooooooooooocooc IIo 12 

22 TITANIUM 4E oooooooooocoooc IIo 1 2 

23 VANADIUM ooooooooocococe IIo 12 

23 VANADIUM 51 ooooooooooooooo IIo 13 

24 CHROMIUM ooooooooooooooo IIo 1 3 

24 CHROMIUM 5 C oooocoooooooooo IIo 16 

24 CHROMIUM =2 ooooooooooooooo IIo 1 6 

24 CHROMIUM 53 ocooocooooooooo IIo 1 6 

2 = MANGANESE 54 ooooooooooooooo lie 16 

25 MANGANESE 55 oooooooooooococ lie 1 7 

26 IRON ooooooooooooooo lie 17 

26 IRON 54 oooooooocoooooo IIo 21 

26 IRON 56 ooooooooooooooo IIo 21 

26 I RON 57 ooooooooooooooo IIo 22 

26 IRON 58 oooooooooocoooo IIo 22 

27 COBALT 56 ooooooooooooooo IIo 22 

27 COBALT 55 ooooooooooooooo I I 0 22 

27 COBALT 60 ooooooooooooooo IIo 23 

26 NICKEL oooooooooooooco IIo 23 

26 NICKEL 58 ooooooooooooooo IIo 25 

26 NICKEL 55 ooocooooooooooc IIo 26 




26 NICKEL 64 ooooooooooooooo lie 27 

25 COPPER 63 oooooooooocoooo Ilo 27 

25 COPPER 65 ooooooooooooooo lie 28 

3 C ZINC 64 oooooooooocoôoo IIo 28 

31 GALLIUM oooooooooocoooo IIo 29 

31 GALLIUM 65 oooooocooooocoo IIo 29 

33 ARSENIC 7= ooooooooooccooo IIo 29 

36 KRYPTON 63 ooooooooooooooo IIo 29 

36 KRYPTON 64 oooooooooocoooo IIo 29 

37 RUBIDIUM E5 oooo oooooocoooo lie 29 

35 YTTRIUM 65 oooooooooooooo0 IIo 29 

4C ZIRCONIUM oooooooooccoooo IIo 29 

4 C ZIRCONIUM 50 oooooooooocoooo IIo 30 

40 ZIRCONIUM 51 ocooooooooooooo lie 31 

40 ZIRCONIUM 52 ooooooooooooooo IIo 32 

4 C ZIRCONIUM 53 ooooooooooooooo IIo 32 

4C ZIRCONIUM 54 ooooooooooooooo IIo 33 



41 NIOBIUM 53 ooooooooooooooo IIo 34 

41 NIOBIUM 5= ooooooooooooooo lie 35 

42 MOLYBDENUM oooo ooooooooooo IIo 35 

42 MOLYBDENUM 52 ooooooooooooooo IIo 36 






43 TECHNETIUM 55 ooooooooooooooo IIo 37 

44 RUTHENIUM 101 ooooooooooooooo lie 37 

44 RUTHENIUM 102 oooocoooooooooo IIo 38 

44 RUTHENIUM 103 coooooooooooooo IIo 38 

44 RUTHENIUM 104 ooooooooooooooo IIo 38 

44 RUTHENIUM 106 oooooooooooooco IIo 38 

45 RHODIUM ooooooooooooooo IIo 39 

45 RHODIUM 102 ooooooooooooooo lie 39 

45 RHODIUM 1 05 ooooooooooooooo IIo 39 

46 PALLADIUM 105 ooooooooooooooo lie 39 

46 PALLADIUM 1 07 ooooooooooooooo IIo 40 

47 SILVER ooooooooooooooo IIo 40 

47 SILVER 1C 7 ooooooooooooooo IIo 40 

47 •SILVER 1C 5 ooooooooooooooo IIo 40 

46 CADMIUM ooooooooooooooo IIo 41 

46 CADMIUM 110 ooooooooooooooo IIo 41 

46 CADMIUM 113 ooooooooooooooo IIo 41 

45 IND I UM ooooooooooooooo lie 41 

45 I ND I UM 11 = ooooooooooooooo IIo 41 

50 TIN 126 ooooooooooooooo IIo 41 

51 ANTIMONY 121 ooooooooooooooo IIo 41 

51 ANTIMONY 123 ooooooooooooooo IIo 41 

Il.xiii

51 

51 

52 

52 

52 

£3 

53 

53 

54 

54 

54 

5£ 

55 

56 

58 

59 

6 C 

60 

6C 

60 

6C 

61 

61 

61 

61 

62 

62 

62 

62 

62 

62 

62 

62 

63 

63 

63 

63 

63 

63 

64 

64 

64 

64 

64 

64 

66 

66 

68 

68 

68 

69 

70 

71 

71 

72 

72 

72 

72 

72 

72 

72 

73 

74 

74 

74 

74 

74 

76 

76 

77 

77 

76 

78 

78 

76 

7S 

80 

80 

80 

81 

81 

81 

82 

86 

89 

90 

90 

91 

91 

91 

92 

92 

92 

92 

92 

92 

92 

92 

93 

93 

93 

94 

94 

94 

94 

94 

TARGET 

ANTIMONY 125 

ANTIMONY 127 

TELLURIUM 127 

TELLURIUM 125 

TELLURIUM 132 

IODINE 127 

IODINE 12S 

IODINE 133 

XENON 131 

XENON 133 

XENON 135 

CESIUM 133 

CESIUM 13 5 

BARIUM 13C 

CERIUM 144 

PRASEODYMIUM 141 

NEODYMIUM 143 

NEODYMIUM 145 

NEODYMIUM 146 

NEODYMIUM 147 

NEODYMIUM 146 

PROMETHILM 147 

PROMETHIUM 146 

PROMETHIUM 145 

PROMETHIU'M 151 

SAMARIUM 

SAMARIUM 144 

SAMARIUM 147 

SAMARIUM 149 

SAMARIUM 150 

SAMARIUM 1=1 

SAMARIUM 152 

SAMARIUM 153 

EUROPI UM 

EUROPIUM 151 

EUROPIUM 153 

EUROPIUM 154 

EUROPIUM 155 

EUROPIUM 156 

GADOLINIUM 

GADOLINIUM 155 




GADOLINIUM 16C 

DYSPROSIUM 161 

DYSPROSIUM 164 

ERBIUM 

ERBIUM 167 

ERBIUM 166 

THULIUM 165 

YTTERBIUM 168 

LUTETIUM 175 

LUTETIUM 176 

HAFNIUM 

HAFNIUM 174 

HAFNIUM 176 

HAFNIUM 177 

HAFNIUM 178 

HAFNIUM 175 

HAFNIUM 16C 

TANTALUM 181 

TUNGSTEN 

TUNGSTEN 162 

TUNGSTEN 163 

TUNGSTEN 164 

TUNGSTEN 166 

OSMIUM 166 

OSMIUM 167 

IRIDIUM 151 

IRIDIUM 153 

PLATINUM 

PLATINUM 190 

PLATINUM 152 

PLATINUM 158 

GOLD 197 

MERCURY 156 

MERCURY 200 

MERCURY 2 CI 

THALLIUM 203 

THALLIUM 204 

THALLIUM 205 

LEAD 

RADIUM 226 

ACTINIUM 227 

THORIUM 232 

THORIUM 233 

PROTACTINIUM 231 



URANIUM 232 

URANIUM 233 

URANIUM 234 

URANIUM 235 

URANIUM 236 

URANIUM 237 

URANIUM 236 

URANIUM 239 

NEPTUNIUM 237 

NEPTUNIUM 236 

NEPTUNIUM 23 5 

PLUTONIUM 236 

PLUTONIUM 237 

PLUTONIUM 236 

PLUTONIUM 236 

PLUTONIUM 240

TARGET 

94 PLUTONIUM 241 




95 AMER1CIUM 241 

95 AMERICIUM 242 



56 CLRIUM 242 

56 CLRIUM 243 

56 CURIUM 244 

56 CURIUM 245 

56 CURIUM 246 

96 CLRIUM 24 7 

56 CLRIUM 246 

96 CURIUM 245 

96 CLRIUM 250 

57 BERKELIUM 245 

97 BERKELIUM 250 

98 CALIFORNIUM 245 



98 CALIFORNIUM £52 

98 CALIFORNILM 252 

96 CALIFORNILM 254 

95 EINSTEINIUM 252 

FISSION PRODUCTS 

STEEL 

page 

oooooooooocoooo IIo 93 

ooooooooooooooo IIo 95 





ooooooooooooooo He 99 


ooooooooooooooo IIo100 


ooooooooooooooo Ho 102 


ooooooooooooooo lie 104 


ooooooooooooooo lie 105 

ooooooooooooooo .IIo 1C6 

ooooooooooooooo IIo 1C6 








000600000000000 IIo 110 



oooooooooocoooo IIo 111 

II.xv

II. P. 

DATA REQUEST LIST FOR FISSION REACTOR DEVELOPMENT

1 HYDROGEN 1 NEUTHCN DIFFERENTIAL ELASTIC CROSS SECTION 

72.1 C 01 7 o GO MEV 2Co C MEV 2o OX 1 USA RcSo CASWELL NBS I OOO^j 

Q: MEASUREMENTS AT 3 ENERGIES - 7, 10, AND 20 MEV 

SUGGEST ED r 

O: FOR USE AS STANDARDc 

STATUS 

STATUS 

LAS H0PKINS+ - ND/A 9 137(1971), EVALUATION TO 3C MEVo 

LAS STEWART* - L A - 4 S 74 ( 1 97 1 ) , SUPPLEMENTARY TO NO/A 9o IMPROVED INTERPOLATION CAPABILITIESo 

BRC VO IGNIERc - CEA-F-4632(1974), THEORETICAL REV IE* 1 TO 2' MEV: 

HRV L0M0N+ - PR/C S 1 329(1974), THEORETICAL REVIEW COVERING MEV ENERGY RANGEc 

YOK SHIRATOt - JPJ 36 151 ( 1974 ) , DATA AT 1401 KEV 

WIS BURROWS+ PR/C 7 1306(1973), DATA 24,0 AND 27o2 MEV 

GEL PAUL SEN + - PL/E 29 562(1 969), DATA 1 TO 6 MEVo 

HAR COOKSON+ - NEANDC(UK)-160(1974). IN PROGRESS 14 TO 28 MEVo 

DKL oIN PROGRESS E Tt 15 ME Vo 

WMU SHAMU - WORK IN PROGRF.SSo 

1 HYDROGEN i NEUTRCN ELASTIC CROSS SECTION 

7.2 It 02 1 o 00 E V 1 o 00 KEV 1 USA Nc ST E EN BET 

A: ACCURACY REQUIRED - 0;5 TO I PERCENTc 

M: SUBSTANTIAL MOD IFICATI ON So 

STA TUS 

STATUS 

RPI STOLER+ - PRL 29 1745(1972), DATA 1 KEV TO 1 MEVc 

2 HeL_IUM_3 NEUTRON N, F 

6S1£01 1Oo 0 KFV • 3c 00 MEV loOX 2 USA Pc Be HEMMIG AEC 

O: ABSOLUTE VALUES REOUIREDc 

A: INTERMEDIATE ACCURACY USEFULc 

O: FOR USE AS A SECONDARY STANDARDo 

6S1C0 3 loOO KEV 3o 00 MEV 3oOX 2 USA R3ScCASWELL NBS 

0: ABSOLUTE VALUES REOUIREDo 

A: INTERMEDIATE ACCURACY USEFULc 

O: FOR USE AS A SECONDARY STANDARDo 

692003 1 C'Cc KEV 1 o 00 MEV 2oOX 2 UK BoROSE HAR 

A: ENERGY DEPENDENCE NEEDED MORE ACCURATELY 

O: USED AS A STANDARD IN CROSS-SECTION MEASUREMENTSo 

113001 1COc KEV 1Oo 0 MEV 3cOX 1 INC MoPc NAVALKAR TRM 

0: ENERGY STEPS OF Oc1 MEVc 

0: FOR NEUTRON SPECTRUM MEASUREMENTS WITH SANDWICHED 

HE-3 SPECTROMETERc 

STATUS : STATUS 

GA C0STELL0+ - NSE 29 409(1970). DATA 0o3 TO lol MEV WITH 10 PERCENT ACCURACY: 

GA C0STELL0+ - 70 ANL 74(1970). REVIEWc 

GEL LISKIENt - 72V IENNA 135, FROM EVALUATION OF INVERSE REACTION, DATA Cc 2 To 9 MEVo 

3 LITHIUM 6 NEUTRON ELASTIC CROSS SECTION 

bSJOOe 1o 00 KEV 300o KEV SCOX 1 USA R o S 3 C ASWELL NBS 

o: DIFFERENTIAL ELASTIC MAY 8E REQUIRED AT UPPER END, 

A: ACCURACY TO OBTAIN N,ALPHA TO 2 PERCENTo 

STA TUS 

HAR 

UTTLEY+ - 70 ANL 80( 1970), REV IEWo 

STATUS 

HAR A SAM I+ - EANDC(J)-l3 ( 1969), DATA 1 TO 10 KEV WITH 4 PERCENT ACCURACY,, 

3_LITHIUM_6_ NEUTRCN N, ALPHA 

6S1C0S lo CO KEV 3o 00 MEV 1o OX 1 USA Co E= TILL ANL 

Pc B:HEMMIG 

AEC 

A: ACCURACY OF 3 PERCENT USEFULc 

ENERGY RESOLUTION MUST REPRODUCE TRUE SHAPEo 

O: FOR USE AS A STANDARDc 

65-1011 5C0o E V 3o 00 MEV 3 o0X 1 USA Go Ec HANSEN LAS 

o: FOR USE AS A STANDARD, 

63200.4 So 00 KEV 15c 0 MEV 5oOX 1 GER McKUECHLE KFK 

O: STANDARDc 

o92£0£ lOOo KEV 5o 00 MEV ScOX 3 UK Co Gc CAMPBELL WIN 

Q: SECONDARY ANGULAR DISTRIBUTION REOUIREDc 

0: FLUX MONITOR FOR NEUTRON SPECTRUM MEA SURE MENTSc 

FISSION LIST PAGE IIo 1

3 LITHIUM 6 NEUTRCN N,ALPHA (CONTINUED) 

212302 5=00 MEV Be ROSE 

CcGo CAMPBELL 

HAR 

WIN 

STANDARD FOR CROSS-SECTION MEASUREMENTS AND FOR 

NEUTRON SPECTRUM MEASUREM^NT So 

112002 1 COo IOo 0 MEV C MoPc NAVALKAR TRM 

0: ENERGY STEPS OF Cc1 MEVc 

o: FOR NEUTRON SPECTRUM MEASUREMENTS WI TH SANDWICHSD 

L1-6 SPECTROMETER; 

121200 1 OOo 13c 0 MEV A HcTcMOTZ LAS 

0: ABSOLUTE VALUES REQUIRED BELOW 150 KEVc 

o: FOR USE AS STANDARD BELOW 3 MEVo 

221509 1 Oo 0 KEV 14c 0 MEV R,S-.CASWELL 

A: ACCURACY 1 PERCENT BELOW 100 KEV, 

0: FOR USE AS STANDARD BELOW 3 ME Vo 

3 PERCENT ABOVF.c 

Z22Q3S 1 Oo C- KE V 3o 00 MEV FR Ac SCHMIDT 

O: STANDARDo 

242024 SoOO KEV 1 So 0 MEV 

GoDELEEUW-GIERTS 

MOL 

SECONDARY ANGULAR DISTRIBUTION REQUIRED UP TO 1 

MEV WITH EMPHASIS BELOW 100 KEV AND ABOVE 500 

KEVc 

ANGULAR RESOLUTION - 10'OEGREESc 

NEUTRON ENERGY RESOLUTION - 5 KEV UP TO 15C KEV 

AND 10 KFIV UP TO 500 KEVo 

DETERMINATION OF NEUTRON SPECTRA FROM TRITON 

ENERGY DISTRIBUTIONSo 

STATUS- 

HAS 

HAR 

UTTLEY* - AERE-Pfi/NP IS 511972), EVALUAT10N0 

UTTLEY+ - AERE-PR/NP 20 24(1974), EVALUATlONo 

-STATUS 

HAR 

HAR 

HAR 

CAD 

MHG 

ANL 

IRT 

ORE 

HAS 

NBS 

NBS 

CLEMENT* - AERE-R-7075(1972), DATA 150 KEV TO 3c9 MEVc SANDWICH DETECTORo LOWER THAN OTHER RECENT 

DATAo 

COATES* - 72VIENNA 105. DATA 1 TC 500 KEVo 

COATES+ - AERE-PR/NP 2 0 35(1974), DATA 1o 5 TO 500 KEV 

FORT* - 72 VIENNA 113, DATA 20 KEV TO 1700 KEVo DATA REMAIN PRELIMINARY DUE TO UNCERTAINTY IN 

Ll-6 CONTENT OF GLASS SCI NT ILLATGRSc 

STEPHANY* - USNDC-9 129(1973), PRELIMINARY VALUE AT 964 KEVc 

POENITZo- ZP 2CE 359(1974), DATA 90 KEV TO 1 05 MEV 

FR lESENHANo - INTEL-RT-7C1 1 -001 ( 1974 ) , DATA 1 TO 1500 KEVc HIGHER THAN OTHER RECENT ME. A SURE ME NT So 

0 VcRLEY* - NP/A 221 573( 1974). DATA Oo1 TO lc8 MEV 

LYNNc - EXPERIMENT PLANNED FOR LATE 1975c 

LAMAZEt - IN PROGRESS 200 KEV TO lc 5 MEV RELATIVE TO BLACK OETECTORc 

MEIER* - EXPERIMENT PLANNED NEAR RESONANCE WITH ASSOCIATED PARTICLE TECHNIQUEo 

3 LITHIUM 6 NEUTRON TCTAL ALPHA PRODUCTION CROSS SECTION 

£.91012 1 o 00 KEV 1 So 0 MEV A WoNcMC ELROY HEO 

0: FOR USE AS A FLUENCE MONITORo 

TOTAL HELIUM PRODUCTION FOR MASS SPECTROMETERo 

3 LITHIUM 7 

2ZH.it 4o 00 MEV 6o 00 MEV A RoSoCASWELL NBS 

A: ACCURACY 2 PERCENT FOR INVERSE REACTION, 

O: ENERGY CORRESPONDS TO 10 KEV TO 1 ME V FQR INVERSE 

REACTION B-101N.ALPHA >o 

4 BERYLLIUM 9 NEUTRON NEUTRON EMISSION CROSS SECTION 

651002 1O 80 MEV SoOO MEV Pc BeHEMMIG AEC 

Q: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REOUIREOo 

A: ACCURACY SO MB AT 2-3 MEVo 

RESOLUTION, 5 PERCENT INCIDENT ENERGY, 500 KEV 

OUTGOING ENERGYo 

O: FOR BE MODERATED FAST SPECTRUM REACTORSo 

FOR THERMAL BREEDERS OR CONVERTORSo 

NEUTRON ECONOMY CALCULAT lONSo 

TOTAL CROSS SECTION 

241001 100c 1 5o 0 MEV PcBo HEMMIG 

CoEo CLIFFORD 

STATUS 

A: 

o: 

OHO HAUSLAOENo - CGO-1717, DATA TO 4o5 MEV FOR B-10 AND B-l 1 : 

M: 

AEC 

ORL 

ACCURACY REQUIRED - 3 TO 4 PERCENTo 

FOR SHIELDING EFFECT OF BORON CARBIDEo 

NEW REQUESTc 

FISSION LIST PAGE I Io 2


.741303 100c KEV 15o 0 McV ISoOX 2 USA PcBcHEMMIG AEC 

COECCLIFFORD ORL 

M: NEW REQUEST, 

STATUS 

STATUS 

OHO HAUSLADENo - COO-1717, DATA TO 4o5 MEV FOR 6-10 AND 6-1lc 

5BORON 

1 

_ __NEUTRON_ _ DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

.741005 15c 0 MEV lOcOX 2 USA PcBcHEMMIG AEC 

CoEcCLIFFORD ORL 

A: 15 PERCENT IN ENERGY SPECTRAo 

20 PERCENT IN ANGULAR DISTRIBUTION IF NOT 

ISOTROPICc 

OUTGOING ENERGY RESOLUTION 10 PERCENT, 

M: NEW REQUEST., 

5 BORON NEUTRON TOTAL PHOTON PRODUCTION GROsi'sEcTlON 

.74100.7 1 = 00 KEV 15=0 MEV IScO* 2 USA PoBcHEMMIG AEC 

Co Ec CL I FFORD ORL 

0: ENERGY AND ANGULAR DISTRIBUTION OF PHOTONS WANTEDo 

A: 20 PERCENT IN ANGULAR DISTRIBUTION IF NOT 

ISOTROPICc 

GAMMA ENERGY RESOLUTION 10 PERCENTo 

M: NE* REOUESTc 

5 BORON 10 NEUTRCN TOTAL CRCSS SECTION 

691016 1Oo 0 KEV 1o 00 MEV 1o 0 X 2 USA RoScCASWELL NBS 

0: DESIRED FOR ASSESSING 8- 10(N,ALPHA) STANDARDo 

STATUS 

ST AT US 

K FK SPENCER* - KFK-1S18. DATA 90 TO 42C KEVo 

GLS SYMEt - EANDC

5 BORON 1C NEUTRON N,ALPHA (CONTINUED) 

ZS402S 5o 00 KEV lOoO MEV 1 CCF LoNcUSACHEV FEI 

A: FROM 0 o 5 - ICC KhV ACCURACY 2 tt PERCENT. 

PRIORITY 2 ACCURACY 2OC PSRC^NTO 

o: STANDARD CROSS SECTION BELOW ICC K=Vo 

FOR MORE DETAIL SEE INTRODUCTION, 


STATUS 

STATUS 

HAR SOWERBY* - ^NE 24 323(19701. DATA TO 209 KEV WITH RECOMMENDED CURVE, 

CAD SZABO+ - EANDC(E)-150(1972), IN PROGRESS 10 TO 100 KEV, 

HAR COATES+ - 72VI ENNA 129. PRELIMINARY CATA 1 TO 300 KEV FOR PARTIAL CROSS SECTION FOR PRODUCTION DF 

478-KEV CAMKA RAY, FURTHER WORK PLANNED FCfi LATE 197S, 

GLS SYME + - EANCC(LK)-151 59(1973), PRELIMINARY CATA 0,2 TO 9 MEVc 

IRT FRIcSENHAHN* - INTEL-RT-7C11-001(1974), CATA 1 TO 1500 KEVo 

NBS LAMAZE+ NSE 56 94(1975). BRANCHING RATIO MEASURED AT 790 KEVc 

NBS SCHRACK+ IN PROGRESS 2CC KEV TO 1,5 MEV USING SLACK DETECTOR, 

5 BORON 10 NEUTRCN TOTAL ALPHA PRODUCTION CROSS SECTION 

6S102£ loOC' KEV 18c C MEV lOoOX 1 USA W,N,MC EL ROY HED 

0: FOR USE AS A FLUENCE MONlTORo 

TOTAL HELIUM PRODUCTION FOR MASS SPE C TROME TE Ro 

6 CARBON NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

712003 1 COc KEV 1 5c 0 MEV 3oC-% 2 SWC He HAEGG0LOM AE 

0: FOR FAST CRITICAL SYSTEMo 

STA TUS- 

PAD F A SOLI + - NF/A 2 C 5 305(1 973). DATA FOR 29 ENERGIES BETWEEN 2,1 AND 4,6 MEV: 

K TY GALATI+ - PR/C 5 1508(1972). DATA 3 TO 7 MEVo 

ABD SUCHER+ - LSNDC-11 267(19741, SMALL ANGLE CATA, IN PROGRESS, 

ORL PERCY* - 0RNL-4441 (1969), DATA FOR 13 ENERGIES BETWEEN 4,6 AND 8,6 MEV, 

A NL MONAHAN* - PR 188 1618(1969), DATA TC 2 MEVo 

ANL SMITH* - LSNDC-711973), DETAILED DATA NOW AVAILABLE TO 4 MEVc 

ORL MORGAN* - LSNDC-7 166(1973), WORK UNDERWAY TO 20 MEVc 

OHO KNOX* - COC-1717-6 11973), DATA AT 2,6 MEVc 

DKE GLASGOW* - LSNDC-11 223(1974), DATA 9 TO 10 MEV, TO BE EXTENDED TO 15 MEVc 

BRC HA0UAT+ - 73KIEV, DATA 8 TC 11 MEVo 

6 CARBON NEUTRON CAPTURE CROSS SECTION 

Z4££27 loCC KEV 15o 0 MEV lOcOX 2 FR AoMICHAUOON BRC 

O: FOR CRITICAL ASSEMBLIES, 

6 CARBON 12 NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

651031 4o 00 KEV 5o50 MEV 15o0% 2 USA RcEHRLICH KAP 

0: POLARIZATION OF SCATTERED NEUTRONS WANTEOo 

A: ENERGY RESOLUTION 50 KEVo 

o: NEEDED TO RESOLVE DISCREPANCY BETWEEN THEORY AND 

EXPERIMEN T, 

7 NITROGEN NEUTRON CAPTURE CROSS SECTION 

Z41C0S 1 o 00 KEV loOO MEV 1 Cc OX 2 USA PoScHEMMIG AEC 

0: RESONANCE PARAMETERS NEEDEDo 

A: RESOLUTION 20 PERCENTo 

M: NEW REQUEST. 

7 NITROGEN 14 NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

6S2Q15 loOC- MEV 1 So 0 MEV 2CoO% 2 FR Ac MI CHAuDON BPC 

A: AVERAGE (1-COS) ACCURACY 10 PERCENTo 

ANGULAR RESOLUTION - 2o5 DEGREES UP TO 20 DEGREES. 

5 DEGREES FROM 20 TO 180 DEGREESo 

O: FOR AIR SCATTERING CALCULATIONo 

NEW EVALUATION TO BE DONE IF NEW EXPERIMENTAL 


692016 8o 00 MEV 14o 0 MEV lOoOX 2 SWO HoOoZETTERSTROEM FOA 

A: ENERGY RESOLUTION 0,2 MEVc 

O: SHIELDING, 


7 NITS.OGEN 14 NEUTRGN DIFFERENTIAL ELASTIC CROSS SECTION (CONTINUED) 

STATUS 

STATUS 

NEL BUCHEfit - AD-734877 (1571). SMALL ANGLE SCATTERING 7c 5 TO 9c 5 MEVo 

NEL BUCHER+ - LSNCC-3 211(1972), WORK IN PROGRESS TG 14 MEVc 

ORL KINNEY* - LSNCC-S 141 (1973). IN PROGRESS 4c 3 TO 806 MEV; 

7 NITROGEN 14 NEUTRCN N.2N 

65.50 02 14c 0 MEV 10 c 0 * 3 HUN JcCSIKAI KOS 

A: INCIDENT ENERGY RESOLUTION 200 KEVC 

o: NEEDED FOR NEUTRON ACTIVATION ANALYSIS AND CROSS 

SECTION SYSTEMATICSc 

7 NITROGEN 14 NEUTRON NEUTRCN EMISSION CROSS SECTION 

652*17 4c OC M£V Ac M I CHAUDON BRC 

0: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REOUIREDo 

A: AVERAGE (I-COS) ACCURACY 10 PERCENTo 

o: FOR AIR SCATTERING CALCULATIONo 

NEW EVALUATION TO 8E DONE IF NEW EXPERIMENTAL 


652216 8= CO MEV 14c 0 MEV lOoGX 2 SwD HcOcZETTERSTROEM FOA 

0: SECONDARY ENERGY DISTRIBUTION ALSO USEFULo 

A: ENERGY RESOLUTION C-c 2 MEVo 

0: SHIELDINGc 

7 NITROGEN 14 NEUTRCN N•F 

652520 lc 00 KEV • 15o 0 MEV iOeOX 2 FR Ac MICHAUDON BRC 

0: EVALUATION MAY BE SUFFICIENTo 

NO MEASUREMENTS EXIST FROM 4, 25 TO 1 5 MEVo 

STATUS 

STATUS 

BRC MICHAUDONc - (1569). NC MEASUREMENTS AVAILABLE BETWEEN 4c 25 AND 15 MEV; 

6 OXYGEN NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

16o 0 ME V PCBCHEMMIG 

CcE;CLIFFORD 

o: 

M: 

AEC 

ORL 

NEEDED FOR FAST REACTOR REFLECTOR WORTHSc 

SUBSTANTIAL MODIFICATIONSc 

652*21 

1 o 7C ME V 

EXPERIMENTAL DATA AVAILABLE IN THIS RANGE NOT 

SUFFICIENTLY DETAILED TO ACCOUNT FOR RESONANCE 

STRUCTUREc 

652322 

4c 70 MEV 1 4c 0 MEV 

A: MEASUREMENTS DESIRED IN ENERGY STEPS INCREASING 

FROM 30 TO IOC KEVo 

ANGULAR RESOLUTION 5 TO 10 DEGREE Sc 

0: ONLY FEW MEASUREMENT POINTS AVAILASLEo 

652523 SoOO MEV 1 4o 0 MEV 1 0 o 0 X C HcOc ZETTERSTROEM FOA 

0: SECONDARY ENERGY DISTRIBUTION ALSO USEFULc 

A: ENERGY RESOLUTION Oc2 MEVo 

0: SHI ELD INGc 

71200.4 

100c KEV 1 So 0 MEV SWC He HAEGGBLOM AE 

O: FOR FAST REACTOR CALCULATIONS; 

STA TUS- 

OSL 

NEL 

ORi 

LAS 

LAS 

KZNNEY* - ORNL-4 780 (1S72). DATA FROM 4o3 TO So 7 MEVc 

BUCHER* - LSNDC-1 232( 1972). SMALL ANGLE CATA FROM 7c4 TO 9c 6 MEVc 

FOWLER+ - PR/C 2 124(1970). DATA lo 8 TO 3c4 MEVc 

FOSTER* - LA-DC-1327l (1971), DATA 5 TO 14 MEVo 

FOSTER* - LA-47GO (1972). EVALUATION 5 TO 20 MEV; 

6 OXYGEN NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

IS202S 1 o CO KEV 1 5o 0 MEV lOcOX FR Ac MI CHAUDON BRC 

0: FOR SHIELDING CALCULATION 

8 OXYGEN NEUTRON NEUTRON EMISSION CROSS SECTION 

652525 SoOC MEV 14o 0 MEV lOoOX D HoO;ZETTERSTROEM FOA 

0: SECONDARY ENERGY DISTRIBUTION ALSO USEFULo 

A: ENERGY RESOLUTION Oo 2 MEVo 

O: SHIELDING; 

FISSION 

LIST

8 OXYGEN 16 TOTAL CROSS SECTION 

154516 5o CC KEV 1Oo 0 MEV LcNcUSACHEV F E I 

FROM OCS - ICO KEV ACCURACY 10 PERCENT, 

PRIORITY 2 ACCURACY IS PERCENTo 

FROM Ool - Oc 6 MEV ACCURACY 7oC PERCENT, 

PRIORITY 2 ACCURACY 6c0 PERCENTo 

FROM 0 o 8 - 405 MEV ACCURACY 10 PERCENT, 

PRIORITY 2 ACCURACY 10 PERCENTc 

ABOVE 4c5 MEV REQUIREMENTS 2 TIMES WEAKERo 

NEED FOR FAST REACTOR CALCULATIONSo 

FOR MORE DETAIL SEE INTROOUCTIONc 

NEW REQUESTc 

8 OXYGEN 16 

6S26Q2 14o 0 MEV lOoOX 

A: INCIDENT ENERGY RESOLUTION SCO KEVc 

0: NEEDED FOR NEUTRON ACTIVATION ANALYSIS AND CROSS 

SECTION SYSTEMATICSc 

8 OXYGEN 17 NEUTRON CAPTURE CROSS SECTION 

6S1S01 2 So 3 MV N GoCchANNA CRC 

A: ACCURACY Cc 2 BARNS: 

0: FOR UNDERSTANDING ABSORPTION IN HEAVY WATERo 

8 OXYGEN 18 

661510 

7o 00 

MEV 

lOoOX No STEEN BET 

A: ALPHA ENERGY RESOLUTION Oo 2 MEVc 

O: TO RESOLVE DISCREPANCIES BETWEEN CROSS SECTION 

AND NEUTRON YIELD DATAo 

M: SUBSTANTIAL MOD IFICATIONSo 

692025 4o OC MEV 

7o 50 

MEV 

Cc CEVILLERS 

SAC 

0: SECONDARY ENERGY DISTRIBUTION REOUIREDo 

A: RESOLUTION FOR £ AND E', lot MEVo 

0: FOR SHIELDING OF ALPHA EMITTING SAMPLESo 



9 FLUORINE 

Z22Q3S 15o 0 MEV Co CEV ILLERS SAC 

9 FLUORINE 19 CAPTURE CROSS SECTION 

o: ENERC-Y DISTRIBUTION REOUIREDo 

o: FOR SHIELDING OF ALPHA EMITTING SAMPLESo 

661511 1O 00 KEV loOO MEV lOoGX USA AcMcPERRY ORL 

o: TO CALCULATE NEUTRON LOSS IN MOLTEN SALT BREEDERc 

STATUS 

FOA NYSTROEM+ - PS 4 95(1971), DATA 20 TC 65 KEVc 

ORL MACKLIN* - PR/C. DATA 3 TC 500 KEV TO Bi PUBLISHED 

9 FLUORINE 19 

65J00.4 1 4o 0 MEV N JcCSIKAl KOS 

A: INCIDENT ENERGY RESOLUTION 200 KEVo 

O: NEEDED FOR NEUTRON ACTIVATION ANALYSIS AND CROSS 

SECTION SYSTEMATICSo 

11 SODIUM 22 TOTAL CRCSS SECTION 

741510 1Oo 0 KEV 15o 0 MEV 1 USA PoBohEMMIG AEC 

Co Eo CLIFFORD ORL 

STATUS 

BNW FOSTER* - FR/C 3 576(1971), DATA 2o5 TO 15 MEVo 

RPI CLEMENT* - RPI-328-218 7(1971), ,7 TO 40 MEVc 

COL RAHN* - USNDC-1 59(1972), WORK IN PROGRESSo 

A: ACCURACY BELOW 7 MEV - 2 TO 5 PERCENTo 

ACCURACY ABOVE 7 MEV - 5 PERCENTo 

M: NEW REQUESTo 

USA (1974), USNOC BELIEVES CROSS SECTION IS PROBABLY KNOWN TO 5 PERCENT UP TO 1 MEVo REQUESTS FOR 

CATA OF e-PEKCENT ACCURACY MUST REFER TC CROSS- SECTION WINDOWS OR REQUIRE FINER RESOLUTION. 

WHICH SHOULD BE SPECIFIED EXPLICITELYo 



652332 2o 20 MEV 10c 0 MEV FoWELLER KFK 

SEPARATION OF ELASTIC AND INELASTIC ANGULAR 

DEPENDENCES DESIREDo 

MEASUREMENTS IN STEPS O c SEVERAL 100 KEVc 

ACCURACY REQUIRED TO BETTER THAN 10o PERCENTo 

INCIDENT NEUTRON RESOLUTION IOC KEVo 

ANGULAR RESOLUTION 5 - 1 0 DEGREESo 

BECAUSE OF RESONANCES IN TOTAL CROSS SECTION, 

FLUCTUATIONS IN ANGULAR DISTRIBUTION EXPECTEOo 

THEREFORE, MORE EXPERIMENTAL DATA NEEOEOo 

Z41012 1 Oo 0 KEV 

ISoO MEV 1 Co OX Po BeHEMMIG 

CoccCLIFFORD 

AEC 

ORL 

A: 15 PERCENT IN ANGULAR D I STR IBUTI ONo 

M: NEW REQUEST; 

-STATUS 

Ft I 

ALD 

PAD 

ORL 

PAD 

USA 

POPOV* - 71 KIEV 11971), CATA AT 4o4 MEVo 

COLES* - AWRE/C-3/71 , CATA AT 5oO MEVc 

FASOLI+ - EANDC(E)-140 (1971), DATA 8 TO 9 MEVo 

PEREY* - OKNL-4518 (1970). DATA 5o4 TO 8o 5 MEVo 

FA SOL I+ - NP/A 125 227(1969). DATA 1o5 TO'6o4 MEVo 

(1974), USNOC BELIEVES ANGULAR DISTRIBUTIONS ARE KNOWN TO 15 PERCENT UP TO 1 MEVc REQUESTS FOR 

CATA OF 15-PERCENT ACCURACY MUST BE FOR CATA IN WINDOWS OR FOR FINER RESOLUTION, WHICH SHOULD BE 

SPECIFIED EXPLICITELYo 

1 1 SOD I UM 23 NEUTRON ANGULAR DIFFERENTIAL INELASTIC CROSS SECTION 

652,035 4o CO MEV I5o0 MEV 1 Co OX 2 GEfi FcWELLER KFK 

11 SODIUM 22 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

621006 2o00 MEV 

lOoO MEV CoEoTILL 

PcBcHEMMIG 

ANL 

AEC 

TOTAL INTEGRAL OVER 4 PI REQUlREDo 

SPECTRA AT SEVERAL ANGLES IF SIGNIFICANTLY 

ANISOTROPIC 

ENERGY RESOLUTION LESS THAN 10 PERCENT INCIDENT 

ANC FINAL ENERGIESo 

STATUS- 

STATUS- 

-STATUS 

FEI 

ALO 

PAD 

ORL 

PAD 

POFOV+ - 71 KIEV (1971). DATA AT 4c 4 MEVo 

COLES* - AWRE/O-3/71, CATA AT 5 MEV FOR 7 LEVELSo 

FASOLI+ - EANDC(E)-140 (1971). DATA 8 TO 9 MEV AND AT 14 MEVo 

PEREY+ - ORNL-4E18 (1970), DATA 5o4 TO 8o5 MEVo 

FA SOL I+ - NP/A 125 227(1969), DATA lc5 TO 6o4 MEV FOR 3 LEVELSo 

11 SODIUM 23 NEUTRON DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

xizaos 1 5o 0 MEV SWC HoHAEGGBLOM AE 

0: FOR FAST REACTOR CALCULATIONSc 

741014 1 5o 0 MEV PoB;HEMMIG 

Cc EcCLIFFORD 

STA TUS 

FEI POPOV* - 71 KIEV (1971), DATA AT 4o4 MEVo 

ALD COLE S* - AWRE/O-3/71. CATA AT 5 MEV FOR 7 LEVELSo 

PAD FA SOL I+ - EANDC(E)-140 ( 1971). DATA 8 TO 9 MEV AND AT 14 MEVc 

ORL PEREY* - ORNL-4518 (1970). CATA 5o4 TO 8o 5 MEVo 

PAD FA SOL I+ - NP/A 125 227(1969}. DATA 105 TO 6o4 MEV FOR 3 LEVELSo 

M: 

AEC 

ORL 

ACCURACY BELOW 2 MEV - 5 PERCENTo 

ACCURACY ABOVE 2 MEV - 10 PERCENTo 

IS PERCENT IN ENERGY SPECTRAo 

OUTGOING ENERGY RESOLUTION 10 PERCENTo 

NEW REQUESTo 

11 SODIUM 23 NEUTRON CAPTURE CROSS SECTION 

642002 lOOo EV 100c Co Go CAMPBELL WIN 

A: ACCURACY 10 PERCENT UP TO 10 KEV. 20 PERCENT 

ABOVEo 

o: FOR FAST REACTORSc 

DISCREPANCY IN RADIATION WIDTH DATA AT 3 KEV 

RESONANCEo 

632038 50o0 KEV P SoKATSURAGI JAE 

a: RESONANCE PARAMETERS NEEDEDo 

O: FOR FAST REACTORSo 

DISCREPANCIES IN RESONANCE PARAMETERS EXISTo 


45 SCANDIUM 45 NEUTRCN CAPTURE CROSS SECTION (CONTINUED) 

2=O 3 MV 4o OC KEV M c N , N IK OL A E V FE I 

CAPTURE wIDTH OF 2-9 KEV RESONANCE SHOULD BE 

MEASURED IN THREE DIFFERENT EXPERIMENTS. RESULTS 

SHOULD COINCIDE WITHIN LIMITS OF 5-7 PERCENTo 

IF HIGH RPI CAPTURE WIDTH CONFIRMED, ENERGY 

DEPENDENCE OF CAPTURE CROSS SECTION SHOULD BE 

MEASURED FROM THERMAL TO RESONANCE REGION TO 

INVESTIGATE INTERFERENCE BETWEEN DIRECT AND 

RESONANCE CAPTURE; 

MEASUREMENTS OF GAMMA RAY SPECTRA IN THERMAL AND 

2:95 KEV REGIONS DESIRABLE FOR DECISION ABOUT 

EXISTENCE OF INTERFERENCE EFFECTSo 

DIRECT MEASUREMENT OF THE EFFECTIVE RESONANCE 

INTEGRAL IN THE SODIUM MEDIUM FROM 24 KEV 

NEUTRON SOURCE SEEMS TO BE USEFUL FOR DECIDING 

THE QUESTION ABOUT THE 2o9 KEV RESONANCE 

CAPTURE WIDTH; 

ACCURACY REQUIRED TO BETTER THAN 1Oo PERCENTo 

FOR CALCULATION OF NA ACTIVATION IN LMFBRo 

SEE ALSO GENERAL COMMENTS IN THE INTRODUCTION 

SUBSTANTIAL MOD IFICATI ON So 

zsioie lo CO KEV 20O CX Po B, HEMMIG 

CoEcCLIFFOPD 

ATC 

OPL 

A: ACCURACY OF C,5 MB OR 20 PERCENT WANTEDo 


Z54C17 5o 00 KEv 19o 0 MEV 1 CCP LcN,USACHEV FEI 

A: FROM 0 c 5 - ICO KEV ACCURACY 44 PERCENT, 

PRIORITY 2 ACCURACY 44 PERCENTo 

FROM Oo1 - Oo 8 MEV ACCURACY 50 PERCENT, 


FROM O08 - 4;5 MEV ACCURACY 50 PERCENT, 

PRIORITY 2 ACCURACY 50 PERCENT, 

ABOVE 4o 5 MEV REQUIREMENTS 2 TIMES WEAKERo 

O: NEED FOR FAST REACTOR CALCULATIONS; 

FOR MORE DETAIL SEE INTRODUCTION 


STA TUS 

STATUS 

BUC PLOS TINARU+ - SCF 25 387(1973). DATA 0 92 TO 4 MEVo 

N PL. RYVES+ - 71 CANT 139, THERMAL; 

AUA CLAYTON - AUJ 23 823( 1970), FITS TOTAL SIGMA NEAR 2C 85 KEV WITH CAPTURE WIDTH OF 0 36 EVc 

RPI YAMA MURO + - NSE 41 445(1 970), 

c INOS CAPTURE WIDTH IS ;47 EV AT 2,85 KEVc 

, RP I HOCKENB URY + - PR * 78 17*6(1 969) , FZNCS CAPTURE WIDTH OF ,4S EV AT 20 65 KEV; 

GA FR IESENHAHN4- - 66WASH 2 69=, FINDS CAPTURE WIDTH OF 0;34 EV AT 2: 85 KEV: 

COL RAHNt - USNDC-3 66(1972), WCRK I IN FRCGRESSo 

ORL ALLEN - WORK IK FROGRESSo 

USA USNDCo (15 74), 2o8 KEVo CAPTURE WIDTH DISCREPANCY REMAINSo 

11 SODIUM 23 NEUTRON CAPTURE GAMMA R AY_SPECTRUM 

Z 2.1032 2o 95 KEV 1 Co OX 1 USA Cc E; T ILL ANL 

STATUS 

STATUS 

ANL JACKSON - FILE SHI ELDED-TA FGET MEASUREMENT IN PROGRESS; 

11 SODIUM 23 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

ZJ101E 2c00 ME V 1 5o 0 MEV Po Be HEMMIG 

CcEc CLIFFORD 

AEC 

ORL 

O: ENERGY AND ANGULAR DISTRIBUTION OF PHOTONS WANTEOo 

A: 2C PERCENT IN ANGULAR DISTRIBUTION IF NOT 

ISOTROPICc 

GAMMA ENERGY RESOLUTION 10 PERCENTo 


11 SODIUM 22 NEUTRON 

Z41020 I60O MEV PcB;HEMM I G 

O: NEEDED FOR COOLANT ACTIVATIONc 


11 SODIUM 23 RESONANCE PARAMETERS 

6Z-120E 

2o 95 

KEV 

CoEcTILL 

PcBcHEMMIG 

ANL 

AEC 

Q: NEUTRON AND CAPTURE WIDTH NEEDEDo 

Z14301 

2o 90 

KEV 

M0N0NIKOLAEV 

FEI 

O: NEUTRON AND CAPTURE WIDTHS WANTEDo 

A: NEUTRON WIDTH FOR 2c 95 KEV LEVEL WANTED WI 

5 PERCENT ACCURACY, 

ALL OTHER WIDTHS REQUIRED WITH 10 PERCENT 

AC CURAC Yo 

O: FOR FAST REACTOR CALCULATION 


11 SODIUM 23 RESONANCE PARAMETERS (CONTINUEO) 

YAL 

K.FK 

RCN 

AUA 

SELTZER* - NSE 53 415(1974). 2o8 KEV, CATA FOR TOTAL PARAMETERS, 

SC HA TZc - KFK-1666 ( 1972), REVIEW 0= RESONANCE PARAMETER DATA 2,8 TO 7

it SUlFUR 3£ NEUTRCN 

65255.3 JSoO MEV T JoBRUNNER WUR 

A: REQUIRED 5c PERCENT ACCURACY To 60 MEV 

AND 10; PERCENT ABOVEc 

O: STANDARD FOR FLUX MFASUREMENTSo 

242125 2o 50 MEV 7o 50 MEV 5 0 0 X NEUTRON DOSIMETRY GROUP 

STATUS 

NEU FOROUGHIt - HPA 45 439(1572). DATA AT 6 MEVo 

NRD RAGOt - HP 14 555(1960). DATA FRCM 2;2 TO 18 MEVc 

FOR NEUTRON DOSIMETSY USING SPECTRUM UNFOLDING 

METHODS; 

GREATER THAN 10 PERCENT DISCREPANCY BETWEEN 

INTEGRAL AND DIFFERENTIAL MEASUREMENTS; 

NDC SCHcTT* - EANDC-95 (1974). COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974o 

17 CHLORINE NEUTRCN N, F 

652554 ICoO KEV 2o 00 MEV lOcOX UK JcSMITH WIN 

O: FOR FUSED SALT REACTORS; 

i 7 CHLORINE 36 TOTAL PHOTON PRODUCT ION CROSS SECTION 

6S22QS LcOcBcAGHINA I EN 

0: GAMMA SPECTRA BETWEEN RESONANCES WANTED; 

0: SPECIAL INTEREST ON INTERFERENCE AND DIRECT 

CAPTURE; 

18 ARGON 40 CAPTURE CROSS SECTION 

1X2ooe 1Oo 0 MEV 

A: ACCURACY REQUIRED TO BETTER THAN 20o 0 PERCENTo 

O: FOR REACTOR HAZARD CALCULATIONo 

18 ARGON 40 NEUTRCN 

dSJflOS 1 4o 0 MEV lOoOX N JcCSIKAI KOS 




19 POTASS IUM 41 

65 3S1£ 1 4o 0 MEV lOo OX N JoCSlKAI KOS 

A: INCIDENT ENERGY RESOLUTION 200 KEVc 


SECTION SYSTEMAT IC So 

20 CALCIUM TOTAL CROSS SECTION 

741.022 lo CO KEV PcBe HEMMIG 

Co Ec CL1FFORD 

AEC 

ORL 

A: ACCURACY REQUIRED - 3 TO 4 PERCENTc 

o: FOR SHIELDING EFFECT OF CONCRETEo 

M: NEW REQUESTc 

MCM 

KFK 

ORL 

ORL 

NBS 

NORMAN+ - CJP 50 2385(1972). DATA 0o8 TO 3o5 MEVo 

NEBE+ - NP/A 185 113(1972). DATA 420 KEV TO 32 MEV 

PEREY+ - 0RNL-4823( 1972), DATA Oc 2 TC 20 MEVo 

JOHNSON* - 0RNL-4844(1573). PRELIMINARY CATA FROM 60 KEV TO 1 MEVo 

BOWMANo HAS DATA 

20 CALCIUM NEUTRON CAPTURE CROSS SECTION 

241025 loOO KEV 500c 1 Oc OX Po BeHEMMIG 

Co Ec CLIFFORD 

AEC 

ORL 

0: FOR SHIELDING EFFECT OF CONCRETEo 


STATUS 

AUA ALLENo - TC BE PUBLISHED IN NUCLEAR FHYSICSo INCLUDES CA-44 RESONANCE CAPTURE FROM 2o5 TO 

167 KEVo 

21 SCANDIUM 45 NEUTRON CAPTURE CROSS SECTION 

£51.065 1 o 00 KEV 18o0 MEV lOoOX 2 USA WcNcMC ELROY HED 




032262 loOC KEV 3o 00 MEV 1 OoOX 2 FR Ac MICHAUDON BRC 

0: PRODUCTION OF SC-46 (84 DAY) 0 

o: DOSIMETRYc 

STATUS 

STATUS 

ORL HALPERINO ( 1974 ) • HAS PROMPT CAPTURE DATAc 

21 SCANDIUM 45 NtEuTRCN N,2N 

6S2061 1 5o 0 MEV 5c OX 2 FR Ac MI CHAUDON BRC 

Q: PRODUCTION OF SC-A4 ( 2o 44 DAY AND 3o 9 HOUR)c 

o: DOSIMETRYc 

STATUS 

STATUS 

ALD MATHER* - AWRE/O-72/72 . VALUE AT 12,3 MEVo 

LRL NETHAWAY - NP/A 190 635(1972), AT 14 MEVc 

21 SCANDIUM 45 NEUTRCN N,ALPHA 

£5.2 .££4 15o 0 MEV lOcOX 2 FR AoMICHAUOON BRC 

Q: PRODUCTION OF K-42 ( 12c 4 HOUR)c 

0: DOSIMETRY:) 

22 TITANIUM NEUTRON ABSORPTION CROSS SECTION 

212007 500c EV 1 So C MEV 25o OX 3 FR JcYoEARRE CAD 

O: FOR FAST REACTOR CALCULATIONSc 

22 TITANIUM NEUTRON CAPTURE CROSS SECTION 

£S2££S lCCc EV 1OOo KEV 20o0% 2 UK Co Gc CAMPBELL WIN 

0: FOR FAST REACTORSc 

202005 50Co EV lc 00 MEV 25o0X 3 FR JcY c EARRE CAC 


STA TUS 

STATUS 

ORL ALLEN* - NCSAC-33 171(1970), DATA 30 KEV TO 3 MEVo 

HAR COATES - MEASUREMENTS TO BEGIN MIO-1975o 

22 TITANIUM NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

£S10£6 1 Cc 0 KEV 16o 0 MEV 20c OX 1 USA CoEo CL! FFOP.D ORL 

0: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REOUIREDo 

O: FOR USE IN REACTOR SHIELDING CALCULATIONSo 

STATUS 

STATUS 

ORL DICKENS* - NCSAC-42 195(1971), WORK IN PBOGRESSc 

22 TITANIUM NEUTRCN N.P 

lisaas 15o 0 MEV 30o0X 3 FR JoYc BARRE CAD 

o: FOR FAST REACTOR CALCULATIONSc 

242118 3o 40 MEV 9o10 MEV SoOX 1 EUR NEUTRON DOSIMETRY GROUP GEL 

ROUTINE FAST NEUTRON FLUENCE MONITOR, 

22 TITANIUM NEUTRON N,ALPHA 

21200S 15o 0 MEV 30oOX 3 FR Jo Yo BARRE CAD 

O: FOR FAST REACTOR CALCULATIONSo 

22 TITANIUM 46 NEUTRON N.P 

£510£S 1o00 MEV 18o 0 MEV lOoOX 2 USA WoNoMC ELROY HED 

0: REQUIRED IS ACTIVATIONo 

DATA REQUIRED AT SCO KEV INTERVALS© 



£52562 1 So 0 MEV lOoOX 2 FR Ao MI CHAUDON BRC 

0: PRODUCTION OF SC-46 (85 OAY)o 

O: ACTIVATION DETECTOR, 

0: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING 

METHODSo 


INTEGRAL AND DIFFERENTIAL MEASUREMENTSo 


22 TITANIUM 66 N5UTRCN N.P (CONTINUED) 

STATUS 

STATUS 

AUB GHORAI+ - JNE as 319(1971). DATA TO 601 MEVo 

NOC SCHETT+ - EANDC-95 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974c 

ANL SMITH+ - ANL/NCM-10 (1975). MEASUREMENTS AND EVALUATION FROM 3c 7 TO 1C MEV 

1AE VLASOV, - (1515) , REVIEW IN PROGRESS: 

22 TITANIUM 47 NEUTPCN N.P 

651021 lc OC MEV I80C MEV 1Oo OX 2 USA WoNc MC EL ROY HEC 

O: REQUIRED IS ACTIVATION; 

DATA REQUESTED IN 1 MEV INTERVALS, 

A: ENERGY RESOLUTION 1 TO KEVo 

O: FOR USE AS A FLUENCE MONITOR, 

652320 1 So 0 MEV 10,CX 2 FR Ac MI CHAUDON BRC 

0: PRODUCTION OF SC-47 ( 3,43 DAY), 


242127 2,10 ME V 7,00 MEV 5,OX 2 EUR NEUTRON DOSIMETRY GROUP GEL 

O: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING 

METHODS, 


INTEGRAL AND DIFFERENTIAL MEASUREMENTS© 

STATUS 

STATUS 

AUB GHORAI+ - JNE 25 319(1971). CATA TO 6c1 MEVc 

N DC SCHETT+ - EANDC-95 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974, 

ANL SMITHt - ANL/NDM-1C (1975). MEASUREMENTS ANC EVALUATION FROM Oc 9 TO 1" MEV; 

JAE GOTOH+ - ( 1575 ). PRELIMINARY DATA 4,1 TO 4:9 MEVo 

IAE VLASOVc - (15 75). REVIEW IN PROGRESS; 

22 TITANIUM 48 NEUTRCN N.F 

6S1C23 1 o OC MEV 16c 0 MEV ICoOX 2 USA WcNcMC EL ROY HED 

0: REQUIRED IS ACTIVATION, 

DATA REQUIRED AT ESC KEV INTERVALSc 


0: FOR USE AS FLUENCE MONITORo 

691324 3c 20 MEV 10c 0 MEV 20o0X 2 USA RoEHRLICH KAP 

O: REQUIRED IS ACTIVATION, 

652322 15o C MEV 10,OX 2 FR A,MICHAUOON BRC 

O: PRODUCTION OF SC-48 (1,63 DAY)c 


242128 60 60 MEV 12,8 MEV 5o OX 2 EUR NEUTRON DOSIMETRY GROUP GEL 

0: FOR NEUTRON COSIMETRY USING SPECTRUM UNFOLDING 

METHODS, 



STATUS 

STATUS 

A Uo GHORAI+ - JNE 2E 319(1571). DATA TO 6c1 MEVo 

NDC SCHETT+ - EANDC-55 (1974). COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974c 

MUN MANNHART+ - ZP 272 279(1975), DATA AT 14 MEVo 

ANL SMITH* - ANL/NDM-1" (1975). MEASUREMENTS AND EVALUATION FROM 4:7 TO 10 MEVo 

I Ac VLASOVo - (1975). REVIEW IN PROGRESS, 

23 VANADI CM NEUTRCN ELASTIC CROSS SECTION 

25 3.S4C 2 5o 3 NV 20o 0 MEV 3o0X 2 INC G0B0GARG TRM 

O: REQUIRED FOR STRUCTURAL-MATERIAL CALCULATIONSo 


23 VANADIUM_ NEUTRON__ DIFFERENTIAL ELASTIC CROSS SECTION 

621305 1 o40 MEV 1 Oc 0 MEV ICoOX 3 USA CcEcTILL ANL 

Po Be HEMMIG 

AEC 


ANGULAR RESOLUTION 10 DEGREESo 

STATUS 

STATUS 

ORL PEREY+ - CKNL-4551 (1970), DATA 4,2 TO 80 6 MEVo 

AE HOLMQVIST+ - NF/A 146 321(1970), DATA 2o5 TO 80C MEVo 

ANL SMITH* - PR/C 1 581(1970), DATA TO 1,5 MEVo 

ANL SMITH* - LSNOC-7 9(19731, WORK IN PROGRESS TO 3o8 MEVc 


2 3 VANADIUM NEUTRCN INELASTIC_CROSS SECTjON 

IZJCAI 2Co 9 MEV 3c OX 2 INC GcBoGARG TRM 

O: REQUIRED FOR STRUCTURAL-MA TE R I AL CALCULATI ONSc 

M: N W REQUEST: 

23 VANADIUM NEUTRON ENfRGY CIF F E n ENT IAL INELASTIC CÔSS SECTION 

fiiiiil 1c 50 NE V 1OcC MEV IScOX 3 USA C,=;TILL ANL 

6a HUTCH IN S 

GE6 

Pc 3c hEMMIG 

AEC 

0: TOTAL INTEGRAL OVER 4 PI REOUIPEDc 


AN ISOTROPIC.: 

STATUS 

STATUS 

Ac ALMEN+ - 7C HELSINKI 2 345(15701. 15 LEVELS FROK 2 TO 4 :5 MEV 

ANL SMITH* - LSNDC-7 5(1573), kCRK IN FFCGRESS TC 4 MEV, 

VANADIUM NEUTRCN ABSORPTION CROSS SECTION 

£ < 1 1 1 5 1 O 00 KEV 150O KEV I:- E3X 3 USA CCE.-TILL ANL 

6c HUTCH INS 

GEB 

Pc 6c hEMMIG 

AEC 

A: ENERGY RESOLUTION 1C PERCENT, 

0: TO RESOLVE DISCREPANCIES IN EXISTING DATA, 

Z1201C SCOc EV 15C 0 MEV 25cCX 3 FR JoY:BARRc CAD 


STATUS 

STATUS 

RPI STIEGLITZ - NF/A 163 552(1571), DATA 19 0 EV TO 200 KEVc 

ORu MACKL1N+ - LSNDC-3 148(1572). DATA 3 TO 590 KEV IN PROGRESS, 

HAR MOXON+ - AERE-FR/NP-17 (1970). EXPERIMENT IN KEV REGION IN PROGRESSc 

HAR COATES - MEASUREMENT PLANNED FOR LATE 1975c 

23 VANADIUM NEUTRCN CAPTURE CROSS SECTION 

6525Z2 100c EV 100= KEV lOcOX 2 UK CcG,CAMP3ELL KIN 

O: FOR FAST REACTORS, 

Z02206 5C0c EV lc 09 MEV 25cOX 3 FR JSY,BARRE CAD 


Z53042 25c 3 MV 20c0 MEV 3oOX 2 INC Go 8, GAR G TRM 

O: REQUIRED FOR STRUCTURAL-MATERIAL CALCULATIONSo 


STATUS 

STATUS 

RPI STIEGLITZ - NF/A 163 552(1571). DATA ICO EV TO 209 KEV, 

OSL MACKLIN+ - LSNDC-3 148(1972), DATA 3 TO 590 KEV IN PROGRESS, 

HAR COATES - MEASUREMENT PLANNED FOR LATE 1975c 

23 VANADIUM NEUTRCN N.F 

I1ZC11 IScO MEV 3C- c 0 X 3 FR Jo Yc BARRE CAD 

o: FOR FAST REACTOR CALCULATIONS, 

23 VANADIUM NEUTRCN N.ALPHA 

I12Z12 15o0 MEV 30 c 0 X 3 FR J c Y:BARRE CAD 

o: FOR FAST REACTOR CALCULATIONSC 

23 VANADIUM 51 NEUTRCN N,ALPHA 

£S2SZ5 1 So 0 MEV 5o 0 X 2 FR Ac MICHAUDON BRC 

O: PRODUCTION OF SC-*8 (1,83 DAY)C 

• O: ACTIVATION DETECTOR: 

STA TUS 

STATUS 

MUN MANNHART+ - ZP 272 279(1975). DATA AT 14 MEVc 

24 CHROMIUM _ NEUTRCN TOTAL CRCSS_SECTION 

Z21035 1o 09 KEV ZOo 0 MEV 3o OX 2 USA Po Be HEMMIG AEC 

A: 5 PERCENT ACCURACY IN DEEP MINIMAO 

ENERGY RESOLUTION SUFFICIENT TO Rr SOLVE MAJOR 

STRUCTUREc 

M: SUBSTANTIAL MODIFlCATIONSo 



241031 1o 00 KEV 20oC MEV 3cOX 2 USA B,HUTCHINS GE3 

A: 5 PERCENT ACCURACY IN DFEP MINIMA, 


STA TUS 

STATUS 

KFK SCHATZc - KFK-1C68 (1972), FEVIEWo 

TUO TRAN UNG* - ZFK-243(1972), DATA 3ol MEV, 

HET GREEN* - WAPD-TM-1073(1973), DATA 0,5 TO 1C MEV, 

ANL WHALEN,- DATA TC 1,5 MEV WITH 2-KEV RESOLUTION, 

24 CHROMIUM NEUTRCN ELASTIC CROSS SECTION 

2520*1 25,3 MV 20,0 MEV 3oOX 2 INC G, E, GARG TRM 

O: REQUIRED FOR STRUCTURAL-MATER I AL CALCULATIONS, 


24 CHROMIUM __ _ NEUTRON 01FFERENTIALELASTIC CROSS SECT!ON__ 

651026 2,00 MEV 14o C MEV 9oOX 2 USA RcEHRLICH KAP 

A: ENERGY RESOLUTION 100 KEV, 

632026 1 o SO MEV 3,00 MEV 15,0X 2 GER Ec GO EL KFK 

A: ABOUT ICO KEV ENERGY RESOLUTION NEEDED, 

ABOUT 10 DEGREE ANGULAR RESOLUTION REQUIRED, 

652322 2o00 MEV 16,0 MEV 20,0% 2 FR C c DEVILLERS SAC 

A: ACCURACY 10 PERCENT PREFERRED, 

ENERGY RESOLUTION 0,5 MEVo 

ANGULAR RESOLUTION 5 TO 10 DEGREES, 

o: EVALUATION MAY BE SUFFICIENT, 

652026 8o OC MEV 16,0 MEV 2GoOX 2 GER B,G0EL KFK 

A: ENERGY RESOLUTION c5 MEVo 

ANGULAR RESOLUTION 5 TO 10 DEGREESo 

231032 100, KEV 15,0 MEV 1 Oo OX 3 USA Po 8, HEMM IG AEC 


STA TUS 

ST AT US 

IJI KORZH* - 72 KIEV, DATA POINT AT 15 MEVo 

IFU PASECHNIK* - YF II 958(1970). DATA TO 4,1 MEVo 

Ac HOLMQvlST* - AE-266 (1965), DATA 2,5 TO 8 MEVo 

AE MALMSKOG - AE-FN-25( 1972), DATA Co 5 TO lo5 MEVc 

ORL KINNEY* - ORNL-480611974), DATA 4o1 TO 8o6 MEVo 

KFK SPENCER* - KFK-1517. DATA 10 TO 3CC KEV, 

ANL SMITH - WORK IN FROGRESSo 

24 CHROMIUM NEUTRON INELASTIC CROSS SECTION 

253032 2Co 0 MEV 3o 0 X 2 INC Go Be GARG TPM 

0: REQUIRED FOR STRUCTURAL-MATERIAL CALCULATIONS, 


24 CHROMIUM^ NEUTRCN ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

66-1012 SCO, KEV 1 5o 0 MEV lOcOX 2 USA B, HUTCH INS GEB 

PcBcHEMMIG 

AEC 

O: TOTAL INTEGRAL OVER 4 PI REQUIREDo 


AN ISO TROP I Cc 

A: ENERGY RESOLUTION REQUIRED TO DETERMINE MAJOR 

STRUCTUREo 

M: SUBSTANTIAL MOD IFICATION So 

232040 15o 0 MEV 20 c 0 X 3 FR JoYoBARRE CAD 

O: FOR FAST REACTOR CALCULATIONS, 

STATUS 

STATUS 

AE ALMEN* - INCC(SEC)-31(1973), IN PROGRESS 2 TO 4=5 MEV, 

ORL KINNEY* - ORNL-4806(1974), CATA 4o1 TO 8o6 MEVo 

ANL SMITH - MEASUREMENTS IN FROGRESSc 

24 CHROMIUM NEUTRCN ABSCRFTION CROSS SECTION 

212514 500c EV 15,0 MEV 5c OX 1 FR JoYc BARRE CAD 

0: FOR FAST REACTOR CALCULATIONSo 


£4 CHROMIUM CAPTURE CROSS SECTION 

652082 100c EV 1 OOo KEV 2CoOX CoG:CAMPBELL WIN 

FOR FAST REACTORSc 

692582 1o CO KEV 

200c KEV lOoOX 

Eo GO EL 

KFK 

RESONANCE PARAMETERS ALSO REQUIRED PARTICULARY 

FOR CR-53c 

ADDITIONAL CAPTURE MEASUREMENTS AND CAPTURE WIDTH 

DETERMINATIONS FOR INDIVIDUAL RESONANCES WANTEDo 

CAPTURE WIDTHS NEEDED BECAUSE OF LARGE 

DISCREPANCIES BETWEEN DIRECTLY MEASURED INFINITE 

CAPTURE RESONANCE INTEGRAL AND THAT CALCULATED 

FROM DIFFERENTIAL CAPTURE MEASUREMENTSo 

6S20B4 ' 5C0= EV 

IcOC MEV 5c OX 

JjY:BARRE 

CAD 

0: NEED OF RESONANCE PARAMETERS FOR THE MAIN 

ISOTOPESc 

O: FAST REACTOR CALCULATIONSo 

EVALUATION AND EXPERIMENT NEEDEDo 

692265 1o 00 KEV 600o KEV 25oCX Cc CEVILLERS SAC 

FOR HEATING AN 0 CIRCUIT ACTIVATION CALCULATI ONc 

EVALUATION MAY BE SUFFIC IENTc 

212915 

A: ACCURACY REQUIRED TO BETTER THAN 20c 0 PERCENTo 

o: FOR FUEL CASK DESIGN AND CONTROL ROD DESIGNo 

721536 loCO KEV lc 00 MEV ISoOX Bo HUTCH IN S 

Po Bo HEMMIG 

CoEiCLIFFORD 

GEB 

AEC 

ORL 

A: ENERGY RESOLUTION 20 PERCENTc 

253533 20o 0 MEV 

C Go Bo GARG TRM 

O: REQUIRED FOR STRUCT URAL-MA TER I AL CALCULA TI ONSo 

M: NEW REQUEST: 

STATUS- 

RPI 

KFK 

CAD 

ANL 

ORL 

HAR 

ST IEGLITZ+ - NF/A 163 592(1971). HIGH RESOLUTION DATA FROM SEPARATED ISOTOPES UP TO 200 KEVo 

BEER* - cANDC(E)-161 90(1974), MEASUREMENTS IN PROGRESS ON SEPARATED ISOTOPESo 

LE RIGOLE LR+ CEA-N-166K 1973) . DATA =RCM 9C TO 538 KEVo 

POENITZo HAS VALUES ABOVE 0o2 MEVo 

HALPERIN+ - DATA BEING ANALYZEDc 

COATES - MEASUREMENT PLANNED FOR MID-1975o 

24 CHROMIUM NEUTRON TOTAL PHOTON PROCUCTION CROSS SECTION 

692060 loOO KEV 1 5o 0 MEV lOoOX Cc DEVILLERS SAC 

Q: GAMMA SPECTRA REQUIREDc 

A: ENERGY RESOLUTION OF 250 KEV FOR GAMMA RAYS LESS 

THAN 1 MfcV AND 500 KEV FOR ENERGIES GREATER 

THAN 1 MEVo 

0: EVALUATION MAY BE SUFFIClENTo 

721032 15o 0 MEV lOoOX 2 USA Po Bo HEMMIG AEC 

Q: ENERGY DISTRIBUTION OF PHOTONS WANTcDo 

ENERGY REQUESTED IS A MAXIMUM VALUE ONLYo 

A: GAMMA-RAY INTERVALS - 500 KEVo 

o: FOR USE IN SHIELDING CALCULATIONSo 


STATUS 

STATUS 

CCP DEGTJAREV+ - IZV 35 2341(1571), DATA 1 TO 3o4 MEVo 

2 4 CHROMIUM NEUTRON NEUTRCN EMISSION CROSS SECTION 

£52075 2o 00 MEV 14c 0 MEV CoDEVILLERS SAC 

Q: SECONDARY ENERGY-ANGLE DISTRIBUTION REQUIREDo 

A: ENERGY RESOLUTION 10 PERCENTo 

O: FOR FAST REACTOR SHIELDING CALCULATIONSo 

EVALUATION MAY BE SUFFIC IENTo 

24 CHROMIUM 

652066 30o 0 X 3 UK CoGoCAMPBELL WIN 

o: FISSION SPECTRUM AVERAGE WANTEDc 

0: FOR FAST REACTORSo 

212516 15o 0 MEV lOoOX 1 FR JoYo BARRE CAD 

STATUS 


UK UKNDC - AVAILABLE ESTIMATES OF FISSICN SPECTRUM AVERAGE DIFFER BY A FACTOR OF 5. MAINLY DUE TO 

UNCERTAINTY IN CR-50(N,P) o 


24 CHROMIUM NEUTRCN N,ALPHA 

66 2.306 3e00 MEV 1 5o 9 MEV 2C = CX 2 FR CoCEVILLERS SAC 

0 : EVALUATION MAY BE SUFFICIENT; 

22 2.041 3; CO MEV 1 So 0 MEV 1C o 9 X 1 FR JcY: BARRE CAD 

o: FOR ÂST REACTOR CALCULATIONS; 

STATUS 

STATUS 

AE WE ITMAN+ - ANS 13 558( 1570). HE PRODUCT ION IN A FISSION SPECTRUM; 

ALD 

c REE MAN + - JNE 23 713( 1569). FISSION SPECTRUM AVERAGE; 

24 CHROMIUM NEUTRON CAPTURE RESONANCE INTEGRAL 

651.027 0 o 59 EV 

RoEHRLICH 

KAP 

0: ENERGY REQUESTED IS A MINIMUM VALUE ONLY; 

REMOVE OR CORRECT FOR (N.P) CONTRIBUTION 

A: ACCURACY REQUIRED - 19 TO 15 PERCENT; 

0: INTEGRAL EXPERIMENT NEEDED TO CHECK RESONANCE 

PARAMETERS; 

M: SUBSTANTIAL MODIFICATIONSc 

STA TUS 

-STATUS 

SPI STIEGLITZ* - NF/A 163 592(1971). 

1c 6 BARNS FROM RESONANCE PARAMETERS; 

;4 CHROMIUM 59 RESONANCE PARAMETERS 

241333 1 C Oc KEV ICoOX 2 USA F; G; PEREY ORL 

0: ENERGY REQUESTED IS A MAXIMUM VALUE ONLYc 

NEUTRON WIDTH, GAMMA WIDTH, SPIN AND PARITY 

WANTEDo 


STATUS 

STATUS 

KFK (1574). DATA FCR 29 RESONANCES FR C N 19 TC 299 KEVo 

ORL HALPERIN* - DATA BUNG ANALYZED; 

24 CHROMIUM 52 NELTRCN N.F 

6S£.cee I5OC MEV 2 GER ECGOEL KFK 

A: ACCURACY 19-20 PERCENT DESIREDo 

0: MAIN ABSORPTION PROCESS IN MEV RANGEo 

STATUS 

S T A T US 

J YV HOLMBERG* - .(IN 26 715(1574), DATA AT 14c 7 MEVc 

24 CHROMIUM =2 NEUTRCN RESONANCE PARAMETERS 

241034 100c KEV lOoOX Fc Gc PEREY ORL 

STA TUS- 

ENERGY REQUESTED IS A MAXIMUM VALUE ONLYo 


WANTED; 

NEW REQUEST; 

AUA ALLEN* - AAEC/PR-39(1974), PRELIMINARY CATA FOR 32 CAPTURE RESONANCES FROM 5 TO 21C KEVo 

K C K (1574), DATA FCR 26 RESONANCES FROM 23 TC 280 KEVo 

ORL HALPERIN+ - DATA BEING ANALYZEOc 

:4 CHROMIUM 53 NEUTRCN RESONANCE PARAMETERS 

es::si lo CO KEV 6 0 9c KEV RcEHRLICH KAP 

Q: NEUTRON WIDTHS WANTEDo 

0: INTEGRAL EXPERIMENT NEEDED TO CHECK RESONANCE 

PARAMETERS, 

M: SUBSTANTIAL MOO IF1CATI ONSo 

741535 

FoGoPEREY 

ORL 

ENERGY REQUESTED IS A MAXIMUM VALUE ONLY 


WANTEDo 

NEW REQUEST- 

-STATUS 

KFK 

RP; 

K FK 

ORL 

MUELLER* - NF/A 164 97(1971). ANALYZES 30 RESONANCES BETWEEN 17 AND 250 KEVc 

STIEGLITZ* - NF/A 163 592(1971), DATA FCR 9 S-WAVE AND 16 P-WAVE RESONANCESo 

( 1574). CATA FCR 57 RESONANCES FRCM 8c 2 TC 250 KEV 

HALPERIN* - DATA BEING ANALYZEDo 

25 MANGANESE 54 NEUTRCN CAPTURE CROSS SECTION 

652192 2 5o 3 MV 5 oO X 2 BLG NcMAENE MOL 

0: FOR BURN-UP CALCULATION OF FE-54(N,P) MN-54 

REACTION PRODUCTo 


£5 ~IANGA.NE.SC 55 TOTAL CROSS SECTION 

74HSS 

F;G:PEREY 

0: NEED VALUES IN FE wINOOWSc 


25 MANGANESE 55 ABSORPTION CROSS SECTION 

212vi? 1 5o C MEV FR Jc Y;EARRE CAD 

0: FOR FAST REACTOR CALCULATIONS: 

25 MANGANESE 55 N5UTRCN CAPTURE CROSS SECTION 

6£2ilC lCCc F:V lC'C; KEV 20= •:• X C;Gc CAMPBELL W: 

o: FOR FAST REACTORS: 

652 050 5 COc EV lo CC MEV 2Ce 0 X J o Y ;EARRE CAD 


ii2si.e 1 Oo 0 MEV 

A: ACCURACY REQUIRED TO BETTER THAN 20;0 PERCENT; 

o: FOR FUEL CASK DESIGN AND CONTROL ROD DESIGNo 

STATUS 

ORL MACKLIN+ - LSNDC-3 148(1572 I. WCRK IN PROGRESS 3 TO 5C0 KEV; 

HAR COATESc - MEASUREMENTS PLANNED FCR EARLY 197fco 

WUx WI DOER - PRECISE DATA FROM OcOl TC 45 EV, TO BE PUBLISHED IN NSE: 

25 MANGANESE 55 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

653012 L LcO;BcAGHINA I EN 

O: GAMMA SPECTRA BETWEEN RESONANCES WANTED; 

O: SPECIAL INTEREST ON INTERFERENCE AND DIRECT 

CAPTURE; 

25 MANGANESE 55 

24212S 13o 0 MEV 5o OX 2 EUR NEUTRON DOSIMETRY GROUP GEL 

O: FOR NEUTRON CDS IMETSY USING SPE CTRUM UNFOLDING 

. METHODS; 


INTEGRAL AND DIFFERENTIAL MEASUREMENTS; 

STATUS 

STATUS 

NOC SCHETT+ - EANDC-55 (1574), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974o 

25 MANGANESE 55 NEUTPCN 

712515 15c 0 MEV 25o 0X 2 FR Jc Yo BARRE CAD 

0: fqr FAST REACTOR CALCULATIONS; 

25 MANGANESE 55 NEUTRON N,ALPHA 

212525 15c 0 MEV 25c OX 2 FR Jc Y;EARRE CAO 

o: FOR FAST REACTOR CALCULATIONS; 

25 MANGANESE 55 NEUTPCN CAPTURE RESONANCE INTEGRAL 

2 4 1 5 3 6 OOSC EV A NCSTEEN BET 

0: ENERGY REQUESTED IS A MINIMUM VALUE ONLYc 

o: NEEDED FOR ANALYSIS OF EXPERIMENTS; 

M: NEW REQUESTC 

NEUTRON TOTAL CROSS SECTION 

212521 500c EV 15c 0 MEV FR Jc Yc BARRE CAD 


214502 1 Co C KEV 1o OC MEV McNcNIKOLAEV FE! 

CAREFUL MEASUREMENTS OF INTERFERENCE MINIMA 

NEEDED; 

OBSERVATION OF P-WAVE RESONANCES IS WANTEDo 

TRANSMISSION MEASUREMENTS WITH POOR RESOLUTICN BU T 

STRONG ATTENUATION OF THE PRIMARY BEAM ARE WANT- 

ED FOR MINIMA CS MEASUREMENTSo 

HIGH RESOLUTION MEASUREMENTS ARE DESIRED FOR P- 

WAVE RESONANCE OBSERVATION AND RESONANCE 

PARAMETER DERIVATION 

FOR SHIELDING CALCULATION NEEDS AND EVALUATION OF 

THE TOTAL AND CAPTURE CROSS SECTIONS FOR FAST 

REACTOR CALCULATI ON Sc 

COMPARISON OF THE S AND P-WAVF LEVEL DENSITIES IS 

VERY INTERESTING FROM THE POINT OF VIE* OF LEVEL 

DENSITY PARITY DEPENDENCE CONFIRMATIONc 

SUBSTANTIAL MOD IFICATIONSo 


26 IRON NEUTRCN TOTAL CROSS SECTION (CONTINUED) 

Z41C3Z 1o CO MV 1o OO MEV USA PoBc hEMM I G 

8s HUTCH INS 

Cc Ec CLIFFORD 

AEC 

GEB 

ORL 

5 PERCENT ACCURACY IN DEEP MINIMA (LESS THAN ONE 

BARN)o 

NEW REQUESTc 

RPI 

COL 

FEI 

ORL 

NBS 

ALFIERI+ - NSE =1 25(1573), DATA AT 24 KEVo 

RAHN+ - NSE 47 272(1572), DATA NEAR RESONANCE MINIMAo 

FILIPOV - YK-e 35(1572). EVALUATION OF HIS OWN AND OTHER DATAc 

HARVEY* - CRNL-4743 52(1971 ) . PRECISE CATA NEAR RESONANCE MINIMA-. 

oNBS—138. CATA Cc 5 TC 16 KEVo 

NEUTRCN ELASTIC CROSS SECTION 

Z53534 2So 3 MV 20o 0 MEV C C-oBcGARG TRM 

O: REQUIRED FOR STRUCTURAL-MATERIAL CALCULATIONSc 


DIFFERENTIAL ELASTIC CROSS SECTION 

£91564 7o 00 MEV 14o0 MEV 9oOX RcEHRLICH 

ENERGY RESOLUTION ICO KEV; 


691.085 3oC0 MEV USA Co Ec CLIFFORD ORL 

0: REQUIRED AT SEVERAL PEAKS AND VALLEYSo 


0: REQUIREO FOR SHIELDINGo 

691066 1 o 00 KEV 1 So 0 MEV lOoOX A CoEoTILL ANL 

A: RESOLUTION AT LEAST TO RESOLVE INTERMEDIATE 

STRUCTUREo 

M: SUBSTANTIAL MODIFICATIONSC 

651587 loOO KEV 1 5o 0 MEV 1 OoOX USA Po Be HEMMIG 


£92094 So OC NE V 1 So 0 MEV lOoOX 

0: MEASUREMENTS DESIRED IN ENERGY STEPS OF 1 MEV. AND 

ANGULAR STEPS OF 10 DEGREESo 

O: FOR SHIELDING C ALCULATI ONSo 

742025 

loOO KEV 1 5o 0 MEV SoOX AoMICHAUOON BRC 

0: FOR CRITICAL ASSEMBLIESc 

STA TUS- 

KGU 

I JI 

TNC 

ORL 

ORL 

A E 

ANL 

Ac 

RPI 

USA 

LESHCHENKO+ YF 15 10(1572), DATA AT 14o MEVo 

K0RZH+ - YFI-12 84(1572), DATA AT 15 MEVo 

TUCKER+ —.NCSAC-42 181(1571). DATA 9 TO 11 MEVo 

PEREY* - ORNL-4515 (1S7CI, DATA 4o2 TO 8o 6 MEVo 

KINNEY+ - ORNL-4807( 1974), CATA 5o5 TO So 5 MEVo 

HOLMQVI S T+ - AE-3 66 ( 19691. DATA 3o TO 8c MEVo 

SMITH* - (1574), DETAILED DATA TO 4 MEVo 

MALMSKOG - EANCC(OR)-115 (1972), IN PROGRESS TO Io4 MEVo 

ZUhRt - (1574), DETAILED DATA TO 600 KEVo 

USNDCo (1914), CONSIDERS CROSS SECTION IS FROBAELY KNOWN TO 10 PERCENT ACCURACY WITH INTERMEDIATE 

ENERGY RESOLUTION TO 4 MEVo 

26 IRON NEUTRON INELASTIC CROSS SECTION 

753035 20o 0 MEV C Go Bo GARG TRM 

O: REQUIREO FOR STRUCTURAL-MATERIAL CALCULATIONSo 


NEUTRCN ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

661516 850O KEV 

2o 00 

MEV 

Bo HUTCH INS 

Po BoHEMMIG 

GEB 

AEC 

TOTAL INTEGRAL OVER 4 PI WANTEDo 


AN ISOTROPICo 

RESOLUTION 20 KEV FOR INCIDENT AND SCATTERED 

NEUTRONSo 

£61016 2o 00 MEV 

5o 00 MEV 1 OoOX 

Be HUTCH INS 

Po Bo HEMMIG 

GEB 

AEC 

O: TOTAL INTEGRAL OVER 4 PI WANTEDo 


ANISOTROPIC© 

A: RESOLUTION 20 KEV FOR INCIDENT AND SCATTERED 

NEUTRONSo 

M: SUBSTANTIAL MOD IFICATIONSo 


26 I HON NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION (CONTINUED) 

732302 14cC MEV FR Jo Yc EARRE CAD 

O: FOR FAST REACTOR CALCULATIONSc 

Z12322 1 5o 0 MEV lOoOX SWC He HAEGG8L0M AE 


Z14004 1 So 0 MEV So OX MoNoNIKOL AEV FEI 

0: IN CONTINUUM REGION ENERGY DEPENDENCE OF NUCLEAR 

TEMPERATURE WANTEDo 

IN THE REGION BELOW 3 MEV AVERAGE CHARACTERISTICS 

0= STRUCTURE IN THE CROSS SECTION ARE WANTED FOR 

EVALUATION OF SELF SHI ELDINGo 

TRANSMISSION MEASUREMENTS USING THE SELF- 

INDICATION METHOD WITH DETECTION OF GAMMA RAYS 

FROM INELASTIC SCATTERING APE DESIREOo 

MEASUREMENTS SHOULD EXTEND TO PRIMARY-BEAM 

ATTENUATION DOWN TO 1/100 OR l/lOOOo 

A: CROSS SECTION FOR INELASTIC REMOVAL BELOW FISSION 

THRESHOLD OF U-238 WANTED WITH 5o0 PERCENT 

ACCURACYo 

LEVEL EXCITATION CROSS SECTION DESIRED WITH 10 

PERCENT ACCURACYo 

0: SEE GENERAL COMMENTS IN THE INTRODUC TI ONo 

M: SUBSTANTIAL MOD IF ICATION So 

-STATUS 

ORL 

AE 

CSE 

ANL 

USA 

KINNEY* - CRNL-4515 (1970). DATA 4 TO 8c5 MEVo 

ALMEN* - INDC(SEC)-31 39(1573). DATA 2 TO 4,5 MEVo 

LINOOW* - NCSAC-31 (1970), DATA 5 TO 5o5 MEVc 

SMITHo ( 1574). CATA TC 4 MEVc 

USNDCo (1574), CONSIDERS DATA WITH 10 PERCENT ACCURACY PROBABLY AVAILABLE UP TO 4 MEVo 

NEUTRCN DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

6S25SE lOeC MEV 

o: 

Cc G:CAMPBELL 

JcBUTLER 

w IN 

WIN 

ACCURACY REQUIRED IS 5 PERCENT TO 4 MEV AND 

5 TO 10 PERCENT ABOVE 

FOR FAST REACTORS AND SHIELDINGo 

Z42030 1 So 0 MEV 5c OX 2 FR Ao M ICHAUDON BRC 


STA TUS 

ORL KINNEY* - C F NL- 4515 ( 1570). DATA 4 TO 8o5 MEVo 

AE ALMEN* - 70 HELSINKI 2 349(1970), DATA FOR 12 LEVELS FROM 2c TO 3o5 MEVc 

CSE LINDOW* - NCSAC-31 (1970), DATA 5 TO 5o5 MEVc 

ANL SMITH* - USNOC-7 9(1973). MEASUREMENTS TO 4 MEV IN PROGRESSc 

26 IRON NEUTRON ABSORPTION CROSS SECTION 

Z12022 5 COo EV 1 5c 0 MEV FR JoY:EARRE CAD 


NEUTRON CAPTURE CROSS SECTION 

6SZ101 1 OOo EV loOO MEV Cc Ge CAMPBELL WIN 

A: ACCURACY REQUIRED 10 PERCENT TO 100 KEV. 

20 c PERCENT ABOVEo 

O: FOR FAST REACTORSc 

692102 loOO KEV 200o KEV F SoKATSURAGI JAE 


DISCREPANCIES EXIST AMONG EXPERIMENTAL DATAo 

692103 1o CO KEV 1 OOo KEV 

0: EXISTING DATA DISAGREE UP TO 2C0 PERCENTo 

STRONG DISAGREEMENT BETWEEN 10 AND 100 KEVc 

692104 5 OOo EV 1o 00 MEV JoYc EARRE CAD 

O: NEED OF RESONANCE PARAMETERS FOR THE MAIN 

ISOTOPESc 


Z12024 1o 00 EV loOO MEV lOoOX D Ho HAEGGBLOM AE 


Z14005 50Co EV SOOo KEV lOoOX MoNoNIKOLAEV FEI 

O: DESIRABLE TO USE EXPERIMENTAL METHODS WHICH ARE 

NOT VERY SENSITIVE TO SELF-SHIELDING AND TO 

CAPTURE-AFTER-SCATTER ING EFFECTSO 

A: 20 PERCENT ABOVE 100 KEV WOULD BE VERY USEFULo 

0: SEE GENERAL COMMENTS IN THE INTRODUCTION, 

FIRST PRIORITY BECAUSE IT IS DIFFICULT TO EVALUATE 

THE IRON CAPTURE CROSS SECTION TO REQUESTED 

ACCURACY FROM MACROSCOPIC EXPERIMENTS ONLY, 

Mi SUBSTANTIAL MODIFICATIONS, 

FISSION LIST PAGE II, 19

26 IRON NEUTRCN CAPTURE CROSS SECTION (CONTINUED) 

Z21035 1,00 MV loOC WEV 1 CcC-X 2 USA RoEHRLICH KAP 

0: VALUES NEEDED IN MINI MA c 

0: SHAPE OF RESOLUTION FUNCTION IMPORTANT SO 

MEANINGFUL BROADENING CAN BE APPLIED TO 

THEORETICAL VALUES TO COMPARE WITH EXPERIMENT,, 

SAMPLE COMPOSITION SHOULD BE KNOWN WELL ENOUGH TO 

PERMIT ISOTOPE SYNTHESIS OF THEORETICAL CROSS 

SECTION, 

FOR SHIELDING CALCULATIONS, 

Z41040 1 o CC KEV lo CO MEV 1 USA F, G, PEREY C L 

Po B,HEMMIG 

AEC 

C , E; T ILL 

ANL 

A: ACCURACY REQUIRED - 5 TO 10 PERCENT, 


.742032 1 o CC KEV 3o OC MEV 10,OX 2 FR Ac MI CHAUDON BO.C 

O: FOR CRITICAL ASSEMBLIES, 

Z53036 2So3 MV 2Oo 0 MEV 3oOX 2 INC G, 8, GARG TRM 

O: REQUIRED FOR STRUCTURAL - MA TE RIAL CALCULATIONS, 


STA TUS 

STATUS 

WIN , (1574) EVALUATION INDICATES 20 PERCENT UNCERTAINTY BELOW 100 KEV, 

CAD LE RIGOLEL'R* - C5A-N-1661(1973). DATA FROM 70 TO 533 KEV, 

HAR PATTENDEN* - AcRE-R-7425 ( 1573) . SEVERAL NEW RESONANCES SEEN IN "TRANSMISSION 

ANL POENITZo (IS 74 ) , DATA ABCVE Co4 MEVo 

ORL HALPERIN* - DATA BEING ANALYZEOo 

HA=i COATES - MEASUREMENTS PLANNED FOR EARLY 1975: 

26 I RON NEUTRCN TCTAL PHOTON PROCUCTION CROSS SECTION 

66.1; 2 2 A P,a,HEMMIG AEC 

0: SECONDARY ENERGY DISTRIBUTION REQUIRED, 

A: ACCURACY REQUIRED TO BETTER THAN 15c PERCENTc 

O: FOR USE IN SHIELDING CALCULATIONS, 

6.92096 1 5o C . MEV Co CEVILLERS SAC 

0: GAMMA SPECTRA REQUIRED, 

A: ENERGY RESOLUTION OF 25C KEV FOR GAMMA RAYS LESS 

THAN 1 MEV AND 500 KEV fqr ENERGIES GREATER 

THAN 1 MEVc 

O: FOR SHIELDING CALCULATI ONSo 

EVALUATION MAY BE SUFFICIENT, 

ORL CICKENS - FR/C 5 100(1572). CATA FROM 5,3 TO 9 MEVc 

CCP KRAVCOV* - 72 KIEV (1972 >o 

GA ORPHAN* - GLLF-RT-10743 (1571). DATA FROM ,9 TO 16,7 MEV, 

KFK VOSS* - 71 KNOXVILLE 218(1571). DATA ,8 TO 13 MEV, 

IRT HARRIS* - WORK IN PROGRESS 4 TC 15 MEV AT 125 DEGREES, 

NEUTRCN 

N.F 

Z12.v2S SWC Ho HAEGGBLOM AE 

0: FOR FAST REACTOR CALCULATIONS, 

Z12C26 1 5o 0 MEV FR JoY,BARRE CAD 

o: FOR FAST REACTOR CALCULATIONSo 

N,ALPHA 

.652105 2So 3 MV 15,0 MEV 20,OX GER EoGOEL KFK 

0: FOR THE THERMAL VALUE ONLY AN UPPER-LIMIT OF Oc 01 

MB IS AVAILABLE, 

65210Z 1 5o 0 MEV 20o OX FR CoDEvILLSRS SAC 

o: EVALUATION MAY BE SUFFICIENT, 

Z32042 15o 0 MEV lOoOX FR JoYo BARRE CAD 


-STATUS 

AE WE ITMAN* - ANS 13 558(1970). HE FKCCUCTION IN A FISSION SPECTRUMo 

ALD FREEMAN* - JNE 23 713(1569). FISSION SPECTRUM AVERAGE, 

FISSICN LIST PAGE IIo 20

NEUTRCN CAPTURE RESONANCE INTEGRAL 

6S1SSS Co 5C EV ROEHRLICH KAP 

0: ENERGY REQUESTED IS A MINIMUM VALUE ONLY; 

REMOVE OR CORRECT FOR (N.P) CONTRIBUTIONo 

A: ACCURACY REQUIRED - 10 TO 15 PERCENT© 

O: INTEGRAL EXPERIMENT NEEDED TO CHECK RESONANCE 

PARAMETERS; 

M: SUBSTANTIAL MOD I F ICA T I ON So 

26 IRON 54 NEUTRON CAPTURE CROSS SECTION 

ZS2S3,5 loOC KEV 3c 00 MEV 1 OoOX FR AcMICHAUDON BRC 

o: ACTIVATION DETECTOR: 

26 IRON =4 NEUTRCN 

6S15S.S 

1 e 00 MEV ia o0 MEV 

1 Oo OX 

WoNcMC ELROY HED 

Q: REQUIRED IS ACTIVATION; 

ENERGY STEPS OF =00 KEVo 



Z 2 1 0 4 4 

1 Co 0 MEV 

1 5o 0 X 

Nc STEEN 

6ET 

0: REQUIREO IS ACTIVATION.; 

ENERGY INTERVALS - 5C0 KEVo 

A: ENERGY RESOLUTION 250 KEV, 

M: SUBSTANTIAL MODIFICATIONS, 

Z4211.S 2o 30 MEV 7o 80 MEV EUR NEUTRON DOSIMETRY GROUP 

0: ROUTINE FAST NEUTRON FLUENCE MONITOR, 

STATUS 

-STATUS 

GCL PAULSEN* - 71 CANTERSY 125(1571), DATA 1 TC 17 MEVo 

JUL QAIM+ - 71CANTERBY 121(1971), DATA AT 15 MEV, 

,NDC SCHETT* - EANCC-55 (1574), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1574c 

ANL SMITH* - ANL/NCX-10 (1575). MEASUREMENTS AND EVALUATION FROM 1,5 TO 1C MEVc 

26 IRON NEUTRCN RESCNANCE PARAMETERS 

Z41C43 lOoOX Fc G;PEREY 

Po 8,HEMMIG 

CcE.TILL 

OFL 

AEC 

ANL 

RPI PANDY* USNCC-11 221(1974), DATA ON TCTAL AND CAPTURE CROSS SECTIONSc 

a: ENERGY REQUESTED IS A MAXIMUM VALUE ONLYo 


WANTEOc 


-STATUS 

26 IRON 56 NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION 

6S3SI4 L L B, AGH IN A IEN 

0: GAMMA SPECTRA BETWEEN RESONANCES WANTED, 


CAPTURE, 

2 6 IRON =6 

t e z a z 8,00 MEV 12c 0 MEV 4o OX 

0: FOR NEUTRON YIELD MONITOR, 

DATA AVAILABLE t PERCENT TO 7 PERCENTo 

6S2111 1 So 0 MEV Ac MICHAUOON 

O: PRODUCTION OF MN-56 (2c58 HOUR), 

0: ACTIVATION DETECTORo 

STA TUS 

GEL EURATOM NELTRCN DOSIMETRY GROUP. CURRENT ACCURACY IS 8 PERCENT, 

-STATUS 

N DC SCHETT* - EANCC-55 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974c 

ANL SMITH* - ANL/NCM-1C (1975), MEASUREMENTS AND EVALUATION FROM 4 TO 1C MEV, 

26 IRON 56 NEUTRON N.ALPHA 

Z2L£ 40 lOoO MEV 1 5, OX USA EoHUTCHINS GEB 

0: TO DETERMINE HE PRODUCTION IN FAST REACTOR So 


26 IRON S< NEUTRON RESONANCE PARAMETERS 

241046 1 OOo KEV lOoOX I 

USA Fo Gc PEREY ORL 

Po6c hEMMIG 

AEC 

COECTILL 

ANL 

O: ENERGY REQUESTED IS A MAXIMUM VALUE ONLYc 


WANT.EDo 

M: NEw REQUESTo 

STATUS 

STATUS 

ORL HALPERINo CATA BEING ANALYZECo 

26 IRON 57 NEUTRON RESONANCE PARAMETERS 

651102 1o 00 KEV 600o KEV 9oOX 1 USA RcEHRLICH KAP 

• a: NEUTRON WIDTH NEEDEDC 

O: NEEDED FOR EVALUATIONS© 

241545 100o KEV ICoCX 2 USA FoG,PEREY ORL 

Po Bo hEMMIG 

AEC 

Cc E:TILL 

ANL 

O: ENERGY REQUESTED IS A MAXIMUM VALUE ONLY© 

NEUTRON WIDTH, GAMMA WIDTH, SPIN ANO PARITY 

WANTEDo 


26,IRON 56 NEUTRON CAPTURE CROSS SECTION 

651104 2 o 00 KEV 2 8© 0 MEV ICoOX 2 USA WoNcMC ELROY HED 

Q: REQUIRED IS ACT I VAT I ON o 

0: FOR USE AS A FLUENCE MONITOR© 

STATUS 

STATUS 

RPI HOCKENBURY* - CSNDC-3 255(2972), WCKK IN PROGRESS Oo2 TC 200 KEVc 

KFK BEER+ - EANDC(E )-l57 ( 1973), EXPERIMENT FLANNECc 

27 COBALT 58 NEUTRCN CAPTURE CROSS SECTION 

22154S ICoOX 2 USA No STEEN BET 

a: WANTED FOR BOTH THE 71c 2 DAY RADIOACTIVE 

AND THE 9c 1 HOUR ISOMERo 

ALL ENERGIESc 

TARGET 

THERMAL CROSS SECTION MOST IMPORTANT© 

RESONANCE INTEGRAL ALSO NEEDEDo 

0: FOR INTERPRETATION OF Nl-58(N,P) FÛENCE 

DATAc 

M: SUBSTANTIAL MOO IFICATIONSc 

MONITOR 

27 COBALT 59 NEUTRON ABSORPTION CROSS SECTION 

212322 5C0c EV 15© 0 MEV 25©CX 3 FR JoY: BARRE CAD 


27 COBALT 59 NEUTRON CAPTURE CROSS SECTION 

651106 1o 00 KEV 18o 0 MEV lOoOX 2 USA WcNcMC ELROY HED 

O: REQUIRED IS ACTIVATION OF BOTH GROUND AND 

METASTABLE STATES, 


Z12026 1 0© 0 MEV 2 JAP MoKAWAI NPG 

A: ACCURACY REQUIRED TO BETTER THAN 20c0 PERCENTo 

0: FOR FUEL CASK DESIGN AND CONTROL ROD DESIGNo 

STATUS 

STATUS 

AUW MLRTY+ - JFJ 35 6(1973). VALUE AT 24 KEVo 

ORL MACKLIN+ - LSNDC-3 148(1972), WORK IN PROGRESS© 

ORL SPENCER* - ABSORPTION DATA BEING ANALYZED© 

27 COBALT 59 NEUTRCN N.F 

652115 15© 0 MEV lOoOX 2 FR Ac MICHAUDON BRC 

Q: PRODUCTION OF FE-59 (45ol OAY)0 

0: ACTIVATION DETECTOR© 

MEASUREMENTS DIFFER BY FACTOR 10© 

Z12025 15© 0 MEV 30o OX 3 FR JoYc BARRE CAD 


STATUS 

STATUS 

ANL SMITH* - ANL/NCM-l0 (1975). MEASUREMENTS AND EVALUATION FROM 4 TO 10 MEVo 

FISSION LIST PAGE llo 22

27 COBALT 55 _ _ NEUTBCN N,ALPHA 

212£J.C 1 So 0 MEV 30o0x 3 FR Jo Yc BARRE CAD 

O: FOR FAST REACTOR CALCULA TIONSc 

STATUS 

STATUS 

NDC SCHETT+ - EANCC-S5 (1974) . COMPILATION OF EXPERIMENTAL CATA AVAILABLE AS OF JANUARY 1974, 

27 COBALT~6 0 NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION 

£5^.516 3 BZL LoOcBoAGHINA IEN 

O: GAMMA SPECTRA BETWEEN RESONANCES WANTEDo 


CAPTUREc 

28 NICKEL NEUTRCN TOTAL CRois SECTION 

721042 1o 00 KEV 20o 0 MEV 3oOX 2 USA CcEoCLIFFORD ORL 

Pc Bo HEMMIG 

AEC 

A: ACCURACY NEEDED TO 3 TO S PERCENT IN DEEP MINIMAo 

ENERGY RESOLUTION SUFFICIENT TO RESOLVE MAJOR 

STRUCTUREo 

0: FOR USE IN SHIELDING CALCULATIONSo 

M: SUBSTANTIAL MODIFICATIONSo 

STATUS 

STATUS 

ANL GUENTHERt - USNCC-11 17(1974). MEASUREMENTS ANC EVALUATION FROM Co3 TO 4 MEVo TO BE PUBLISHED 

ORL PEREYo- PRELIMINARY DATAo INFORMATION FROM NNCSCc 

N8S 

oN8S-138o 

28 NICKEL NEUTRCN ELASTIC CROSS SECTION 

753037 25o 3 MV 20c0 MEV 3oOX 2 INO Gc Bo GARG TRM 

0: REQUIRED FOR STRUCTURAL-MATERIAL CALCULATIONSo 


28 NICKEL _ NEUTRON _ DIFFERENTIAL ELASTIC CROSS SECTION 

591110 1o 50 MEV 14o 0 MEV 9oOX 1 USA RoEHRLlCH KAP 



652120 lo 50 ME'V 3o 00 MEV ISoOX 2 GER EoGOEL KFK 

A." ABOUT 100 KEV ENERGY RESOLUTION AND ABOUT 

5 DEGREES ANGULARo 

RESOLUTION 10 PERCENT ON AVERAGE (COS)o 

£52122 SoOC MEV 1 So 0 MEV 20o0X 2 FR Co DEVILLERS SAC 

A: ACCURACY 10 PERCENT PREFERREDo 

ENERGY RESOLUTION - 500 KEVo 

ANGULAR RESOLUTION - '10 DEGREES, 

0: FOR FAST REACTOR SHIELDING CALCULATIONSo 

EVALUATION MAY BE SUFFICIENT, 

Z 21045 1 OOo KEV 15,0 MEV 2 USA CoEcTILL ANL 

Po Be HEMMIG 

AEC 

A: ACCURACY REQUIRED - 5 TO 10 PERCENTo 

RESOLUTION OF INTERMEDIATE STRUCTURE PROBABLY 

ADEQUATEc 


STATUS 

STATUS 

AE HOLMOVIST • - AE-366(1569). DATA 3 TO 8 MEVo 

ORL PEREY* - 0RNL-4515(1970). CATA 4o2 TO 8,6 MEVo 

AE MALMSKAGo - AS-FN-25(1972) . DATA Oo 5 TO 1o5 MEVo 

RPI ZUHR + - C00-3058-39 22(1973). DATA 50 TO 650 KEVo 

ORL KINNEY* - OSNL-4807( 1974), DATA 4o1 TO 8o 6 MEVo 

ARL VELKLEY+ - PR/C 9 2181(1974), DATA AT 9 MEV, 

ABD BUCHER+ - LSNCC-11 267(1974). SMALL-ANGLE SCATTERINGo IN PROGRESS, 

ANL GUENTHER* - USN'DC-l 1 17( 1974). MEASUREMENTS ANC EVALUATION FROM Oo 3 TO 4 MEVo TO BE PUBLISHED 

2 8~NICKEL NEUTRON _ INELASTIC CROSS SECTION 

2Z2B2S 20o 0 MEV 3,OX 2 INC Go Bo GARG TRM 

O: REQUIREO FOR STRUCTURAL-MATER IAL CALCULATIONS, 



i8 NICKHL ENERGY C IFFERENT IAL INELASTIC CROSS SECTION 

6-61I2S 15c 1 Co OX B;HUTCHINS 

PcBo HEMMIG 

GEB 

AEC 

TOTAL INT = G-=AL 4 PI REQUIREDo 


AN I SO TROPI C: 

ENERGY RESOLUTION - 10 PERCENT FOR INCIDENT AND 

SCATTERED NEUTRON REQUIRED TO DETERMINE MAJOR 

STRUCTURE: 


.7.02.006 15o0 MEV FR JoY;BARRE CAD 


STA TUS 

CFNL-4515(197C), DATA 4,2 TO 8c6 MEVo 

ORL PEREY+ 

A

TOTAL PHOTON PRODUCTION CROSS SECTION (CONTINUED) 

692X2S lo 00 KEV 1 So 0 MEV 1Oo OX 2 FR CoCEVILLERS SAC 

0: GAMMA SPECTRA REQUIRED, 

A: ENERGY RESOLUTION OF 250 KEV FOR GAMMA RAYS LESS 

THAN 1 MEV AND SCO KEV FOR ENERGIES GREATER 

THAN 1 MEVo 

O: FOR FAST REACTOR SHIELDING CALCULATIONSo 

EVALUATION MAY BE SUFFIC IENTc 

Z2XH52 2 So 3 MV 1 Oo C MEV 20 o OX 2 USA PcBcHEMMIG AEC 

O: SECONDARY ENERGY DISTRIBUTION REQUIRED, 

o: FOR SHIELDING AND GAMMA HEATING CALCULATIONSo 

STATUS 

STATUS 

ORL CICKENSo - ORNL-TM-4379. DATA 1 TC 2C MEVo 

28 NICKEL NEUTRON NEUTRON EMISSION CROSS SECTION 

6i2X23 2o GC KEV 1 So 0 MEV Co DEVILLERS SAC 

Q: SECONDARY ENERGY DISTRIBUTION FEQUIREDc 

A: RESOLUTION FOR PRIMARY AND SECONDARY NEUTRONS 

10 PERCENT, 

o: FOR FAST REACTOR SHIELDING CALCULATIONSo 

EVALUATION MAY BE SUFFICIENTo 

28 NICKEL N, F 

Z02010 15o 0 MEV lOoOX FR JoYo EARRE CAD 


28 NICKEL 

£S2X32 1 5o 0 MEV 20o OX CcOEVILLERS 



Z21051 1 Oc 0 MEV 1 5oOX A B,HUTCH INS GEB 

O: TO DETERMINE HE PRODUCTION IN FAST REACTORSo 

Z223Sa 1 5c 0 MEV 1 FR JoY,BARRE CAD 


2 8 NICKEL NEUTRCN 

CAPTURE RESONANCE INTEGRAL 

6SH0S 0,50 EV USA RcEHRLICH KAP 

O: REMOVE OR CORRECT FOR N.P CONTRI BUT IONc 

28 NICKEL 56 

652X33 1 5o 0 MEV Ac MICHAUDON 8RC 

0: PRODUCTION OF N1-57 (36,4 HOUR), 



DISAGREEMENT BETWEEN JERONYMOC SACLAY) AND OTHERS, 

28 NICKEL 56 NEUTRCN 

Z2XOSS 1 5o 0 MEV USA 

0: FOR USE AS FAST FLUENCE MONITORc 

SUBSTANTIAL MOD 1FICATION So 

Z321U NEUTRON DOSIMETRY GROUP GEL 

O: AVERAGE CROSS SECTION IN A U-235 FISSION SPECTRUM 

DESIREDc 

o: FOR NORMALIZATION OF AVERAGE CROSS SECTIONS FOR 

DOSIMETRY PURPOSES, 

ZA2XX1 2o 10 MEV 7o 00 MEV 5oOX 1 EUR NEUTRON DOSIMETRY GROUP GEL 

0: ROUTINE FAST NEUTRON FLUENCE MONITORo 

STRONG DISCREPANCY BETWEEN DIFFERENTIAL DATA AND 

AVERAGE VALUE IN U-235 FISSION NEUTRON SPECTRUMc 

STATUS 

STATUS 

IRK WAGNER* - APA 37 288(1973). DATA 2 TO 20 MEVo 

GEL PAULSEN* - EANDC(E)-150 (1972), MEASUREMENT IN PROGRESSo 

N DC SCHETT+ - EANCC-95 ( 1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974, 

ANL SMITH* - ANL/NDM-10 (1975). MEASUREMENTS AND EVALUATION FROM Oc4 TO 10 MEVc 


28 NICKEL 56 NEUTRCN N.NF 

652136 1 So 0 MEV lOoOX 2 FR #0M ICHAUDON BRC 

Q: PRODUCTION OF CO-57 (270 DAY) THROUGH 

SIGMA(N.NP)+SIGMA(N,D)o 

0: ACTIVATION OETECTORc 

CIRCUIT ACT I VATIONo 

DISAGREEMENT BETWEEN JERONYMO(SACLAY) AND OTHERSo 

28 NICKEL 58 NEUTRCN N.ALPHA 

652.135 14o 0 MEV 2 GER Be GOEL KFK 

A: ACCURACY REQUIRED TO BETTER THAN 20o PERCENTo 

0: VERIFICATION OF EVAPORATION THEORY CALCULATIONSo 

STATUS 

STATUS 

NDC SCHETT+ - EANDC-S5 (1974) , CCMPILATICN OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974c 

28 NICKEL 58 NEUTRON RESONANCE PARAMETERS 

241.056 100c KEV lOoOX 2 USA FoGoPEREY ORL 

PoBohEMMIG 

AEC 

Co Ec TILL 

ANL 

O: ENERGY REQUESTED IS A MAXIMUM VALUE ONLYo 

NEUTRON WIDTH. GAMMA WIDTH. SPIN AND PARITY 

WANTEOo 


STATUS 

STATUS 

ORL HALPERINo - MEASUREMENTS PLANNED FOR 1975o 

28 NICKEL 59 _ NEUTRCN _ N,ALPHA 

242523 2Eo3 MV 500o EV 20o0X 2 BLC NoMAENE MOL 

A: EVEN AN ACCURACY OF 50 PERCENT WOULD BE USEFULo 

0: EVALUATION OF HE PRODUCTION IN STEEL IN HIGH FLUX 

REACTORS THROUGH THE REACTION CHAIN 

N1-58(N . GAMMA>NI-59(N,ALPHA)FE-56o 

STATUS 

STATUS 

MOL MAENE - ThEORETICAL EVALUATION OF THERMAL CROSS SECTION BY KIROUAC (NSE 46 427) YIELDS 30 BARNS. 

TO BE COMPARED WITH A VALUE OF 11 EARNS DEDUCED BY WEITMAN FROM ANOMALOUS HELIUM PRODUCTION 

RATE IN STEEL IRRADIATED IN A FILE SPECTRUMo 

28 NICKEL 60 _ NEUTRON _ N,P 

652132 15c 0 MEV lOoOX 2 FR Ao MICHAUDON BRC 

Q: PRODUCTION OF C0-60 (5c 3 YEAR) o 

0: ACTIVATION OETECTORo 

28 NICKEL 60 _ NEUTRCN N.ALPHA 

6S2l3£ 14o 0 MEV 2 GER BoGOEL KFK 


0: VERIFICATION OF EVAPORATION THEORY CALCULATIONSo 

28^NICKEL 60 NEUTRON _ RESONANCE PARAMETERS 

131S5S lOOo KEV lOoOX 2 USA FoGoPEREY ORL 

PoBohEMMIG 

AEC 

CoEcTILL 

ANL 

Q: ENERGY REQUESTED IS A MAXIMUM VALUE ONLYo 

NEUTRON WIDTH. GAMMA WIDTH, SPIN AND PARITY 

WANTEDo 


STATUS 

STATUS 

ORL HALPERIN* - MEASUREMENTS PLANNED FOR 1975o 

28 NICKEL 61 NEUTRCN RESCNANCE'PARAMETERS 

651125 lo 00 KEV 600o KEV 9,OX 1 USA ROEHRLICH KAP 

Q: NEUTRON *IDTh NEEDEDo 

241062 1 OOo KEV lOoOX 3 USA FoGoPEREY ORL 

PoBohEMMIG 

AEC 

CoEoTILL 

ANL 

Q: ENERGY REQUESTED IS A MAXIMUM VALUE ONLYc 


WANTEOo 


FISSION LIST PAGE 26

28 NICKEL 61 NEUTRCN RESONANCE PARAMETERS (CONTINUED) 

STATUS 

KFK ERNST* - KFK-1231 (1970). CAPTURE WIDTHS FOR 14 RESONANCESo 

KFK CHO + - KFK-123C (1970) . NEUTRON WIDTHS ANC Jc 

RPI HOCKENBURY* - LSNDC-3 155(1972), WORK IN FROGRESSo 

KFK BEER* - KFK-1272 3(1972), WCRK IN FRCGRESSo 

RPI PANDY+ - DATA AVAILABLEo 

: 

STATUS 

28 NICKEL 62 NEUTRCN CAPTURE CROSS SECTION 

££2013 1o 00 KEV 1o OC MEV 20oOX 2 FR Ao MICHAUDON BRC 

STA TUS 

0: PRODUCTION OF N 1-63 (92 YEAR )o 


KFK BEER* - EANDC(E)-157 (1973), MEASUREMENT RELATIVE TO GOLC IN PROGRESS 5 TO 200 KEVo 

STATUS 

28 NICKEL 62 _ NEUTRCN RESONANCE PARAMETERS 

2410££ 1 OOo KEV lOoOX 3 USA FoGoPEREY ORL 

PoBo HEMMIG 

AEC 

CoEoTILL 

ANL 

0: ENERGY REQUESTED IS A MAXIMUM VALUE ONLYo 

NEUTRON WIDTH, GAMMA WIDTH. SPIN AND PARITY 

WANTEDo 

M: NEW REOUESTo 

28_NICKEL 64 __ ^NEUTRCN CAPTURE CROSS SECTION 

££.2014 1 o 00 KEV 1 o 00 MEV 20 o OX 2 FR Ac MI CHAUDON BRC 

O: PRODUCTION OF N 1-65 ( 2o 56 HOUR )c 


STATUS 

STATUS 

KFK BEER* - EANCC(E)-157 (1973). MEASUREMENT RELATIVE TO GOLD IN PROGRESS 5 TO 200 KEVo 

28 NICKEL 64 NEUTRCN N.2N 

£52135 15o 0 MEV lOoOX 2 FR Ao MICHAUDON BRC 

O: PRODUCTION OF N1-63 (92 YEAR)o 

O: ACTIVATION DETECTORo 

28NICKEL 64 _ _NEUTR0N_ RESONANCE PARAMETERS 

241££e 1 OOo KEV 1Oo OX 3 USA Fo Gc PEREY ORL 

Po Be HEMMIG 

AEC 

CoEcTILL 

ANL 

0: ENERGY REQUESTED IS A MAXIMUM VALUE ONLYo 

NEUTRON WIDTH. GAMMA WIDTH, SPIN AND PARITY 

WANTEOo 


29 COPPER 63 _ NEUTRON CAPTURE CROSS SECTION 

£21001 25o3 MV lo 00 KEV 2 USA Po Bo HEMMIG AEC 

A: ACCURACY 2 PERCENT NEAR THERMAL. 5 PERCENT ABOVE 

THERMALo 

O: FOR DETECTOR APPLICATIONSo 

691132 1o 00 KEV 18o 0 MEV lOoOX 2 USA WoNoMC ELROY HED 

Q: REQUIRED IS ACT IVATIONo 


222043 1Oo 0 KEV 3o OX 2 FR Ho T ELL IER SAC 

O: DETECTORo 

STATUS 

STATUS 

HAR MOXON+ - AERE-FR/NP13 (1968). MEASUREMENTS IN PROGRESS TO 100 KEVo 

ORL MACKLIN* - NCSAC-42 185(1971). MEASUREMENTS IN PROGRESS TO 500 KEVo 

RPI PANOY+ - CATA EEING ANALYZED© 

29 COPPER 63 NEUTRON _ N^2N 

68201E 12o 0 MEV 5oOX 1 JAP YoKANOA KYU 

o: FOR NEUTRON YIELD MONITORo 

A FEW DATA AVAILABLEo 

££201C 14o0 MEV 20o 0 MEV 5oOX 1 JAP YoKANDA KYU 

0: FOR NEUTRON YIELD MONITORo 

LARGE DISCREPANCIES AMONG DATAo 


2 9 COPPER 62 NEUTRCN N,2N (CONTINUED) 

242130 1lo9 ME V 16o 4 MEV 5 = OX 2 EUR NEUTRCN DOSIMETRY GROUP GEL 


METhODSo 



STA TUS 

STATUS 

NDC SCHETTt - EANDC-S5 (1974), CCMFILATIGN OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974c. 

29 COPPER 63 NEUTRCN N,ALPHA 

£51135 6o 00 MEV 18oC MEV ICoOX 2 USA WcNcMC ELROY HED 

0: REQUIRED IS ACTIVATIONc 


242120 6o 1 0 MEV 11,3 MEV SoOX 1 EUR NEUTRON DOSIMETRY GROUP GEL 

O: ROUTINE FAST NEUTRON FLUENCE MONITORo 


GEL LISKIEN+ - JNE 27 39(1973). DATA AT 8o1 MEVo 

MAM BORMANN+ - hlP/A 186 65(1 972). DATA AT 14 MEVc 

NDC SCHETT+ - EANCC-95 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974c 

29 COPPER 65 NEUTRCN CAPTURE CROSS SECTION 

621CQ2 25o3 MV lc CO KEV 2 USA P0B7HEMMIG AfcC 

A: ACCURACY 2 PERCENT NEAR THERMAL, 5 PERCENT ABOVEc 

O: FOR DETECTOR APPLICATION So 

STATUS 

STATUS 

HAR MOXONt - AERE-PR/NP13 (1968), MEASUREMENTS IN PROGRESS TO 100 KEVc 

ORL MACKLIN+ - NCSAC-42 185(1971), MEASUREMENTS IN PROGRESS TO 50C KEVo 

2 9^ COPPER 65 NEUTRCN N^ 2M 

682517 12e 0 MEV BoOX 1 JAP YoKANDA KYU 


6£201B 1 5o 0 MEV 2 Co 0 MEV SoOX 1 JAP YoKANDA KYU 


LARGE DISCREPANCIES AMONG DATAo 

STATUS 

STATUS 

JUL QAIM - NP/A 165 614(1972), DATA AT 15;0 MEVc 

HAM MOGHARRAB+ - AKE 19 107(1972), DATA AT 14 MEVo 

JAE KANOAt - JAERI-1207 (1972). EVALUATION 11 TO 20 MEVo 

LOU ARAMINOWICZ+ - INR-1464 (1973), DATA AT 14 MEVo 

NPL ROBERTSON* - JNE 27 531(1973), DATA AT 15 MEVo 

MUN MANNHART+ - ZP 272 279(1975), DATA AT 14 MEVc 

NOC SChETTt - EANDC-95 (1974), COMPILATICN OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974o 

30ZINC64 NEUTRCN ^ * f lb? Sf ° S §_ § i 

102012 24o0 KEV lOoOX 3 JAP HoNAKAMURA FE 

0: FOR NORMALIZATION OF THE CALCULATED CROSS SECTION 

CURVEo 

30 ZINC 64 NEUTRCN N.2N 

653516 1 4o 0 MEV lOoOX 3 HUN JoCSIKAI KOS 



SECTION SYSTEM AT I CSo 

30 ZINC 64 NEUTRCN N. F 

242131 2=30 MEV 7o 80 MEV SoOX 2 EUR NEUTRON DOSIMETRY GROUP GEL 


METHODSo 

ABOUT 20 PERCENT DISCREPANCY BETWEEN INTEGRAL 

AND DIFFERENTIAL MEASUREMENTSo 

STA TUS 

STATUS 

NDC SChETTt - EANDC-S5 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974o 

ANL SMITH* - ANL/NDM-10 (1975). MEASUREMENTS AND EVALUATION FROM lcl TO 10 MEVo 


3 1 GALLIUM NEUTRCN N, 2N 

742£36 15o 0 MEV 20c ;x 2 FR Ac MICHAUDON 5RC 

31 GALLIUM 69 NEUTRCN N , 2N 

65.3C1S 14oC HF.V 1 OoOX 3 HUN 

Jc CS1KAI 

KOS 

A: 

o: 

INCIDENT ENERGY RESOLUTION 20C KEVc 

NEEDED FOR NEUTRON ACTIVATION ANALYSIS AND CROSS 

SECTION SY STE MAT 1 C S, 

33 ARSENIC 75 NEUTRCN 

652145 i 5c C MEV 1 Oc OX 3 FR 

Ao MICHAUDON 

BRC 

0: 

o: 

PRODUCTION OF AS-74 ( 17c 5 OAYlo 

ACTIVATION CETECTCS, 

36 KRYPTON 83 NSuTRON TOTAL CROSS SECT ION 

621 US 1 o 00 MV 1,09 KEV lOcCX 2 USA 

Nc ST£EN 

RoEhRLICH 

EFT 

KAP 

A: 

o: 

ENERGIES ABOVE 1 EV CF INT£R=ST TO GIVE RESONANCE 

INTEGRAL TO 1 C PFRCENTo 

FOR FISSION PRODUCT ABSORPTION CALCULATION, 

36 KRYPTON 83 NEUTRON CAPTURE CROSS SECTION 

bixxas iooo MV lc OC KEV ICoOX 2 USA 

NcSTEEN 

ROEHRLICH 

BET 

KAP 

o: 

A: 

o: 

M: 

THERMAL CROSS SECTION AND RI WANTEDc 

ENERGIES ABOVE 1 EV O c INTEREST TO GIVE RESONANCE 

INTEGRAL TO 10 PERCENT, 

FOR FISSION PRODUCT ABSORPTION CALCULATIONo 

SUBSTANTIAL MODIFICATIONS, 

36 KRYPTON 64 N5UTRCN CAPTURE CROSS SECTION 

24204C loOO KEV 3o OC MEV lOoOX 1 Ffi 

Ac MICHAUDON 

BRC 

o: 

FOR 

ACTIVATIONo 

3 7 RU6I0IUM 85 NEUTRCN N,2N 

65214,7 I Oo 0 MEV 15oC MEV 5o0 X 2 FR 

Ac M ICHAUDON 

BRC 

o: 

0: 

PRODUCT ION OF R6-84 (33 DAY), 

ACTIVATION DETECTOR, 

STATUS 

HAM 80 FM ANN + - EANCC< E)-150 ( 1972). ACT I VAT ION MEASURE McNT IN PROGRESS 13 TO 18 MEVo 

AUB GH0RAI + - NF/A 223 118(1574 I , DATA AT 3 ENERGIES FROM 15 TO 17 MEV: 

39 YTTRIUM 89 NEUTRON CAPTURE CROSS SECTION 

652£15 loOC KEV 3oOO M£v 1C = 0X 1 FR 

AoMlCHAUDON 

BRC 

Q: 

o: 

PRODUCTION OF Y-9C (64c 2 HOURlc 

ACTIVATION DSTECTCRc 

40 ZIRCONIUM NEUTRCN DIFFERENTIAL ELASTIC CROSS SECTION 

651255 2.00c KEV 1o 50 MEV lOoOX 2 USA 

RaEHRLICH 

KAP 

A: 

o: 

ENERGY RESOLUTION 5,0 PSRCENTc 

TO RESOLVE DISCREPANCIES IN EXISTING DATAo 

651296 7o 0 0 MEV 14o 0 MEV 20o0X 2 USA 

RaEHRLICH 

KAP 

A: 

ENERGY RESOLUTION 2:5 PERCENTo 

STATUS 

ANL SMITH - ANL/NDM -4. ISOTOFIC DATA TC 4 MEVo 

40 ZIRCONIUM NEUTRCN ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

7112514 4c 00 MEV 7o 00 MEV 3 JAP 

HcNAKAMURA 

FE 

A: 

o: 

ACCURACY REQUIRED TO BETTER THAN 20,0 PERCENTc 

FOR INVESTIGATIONS OF LEVEL DENSITY PARAMETERS, 

40 ZIRCONIUM NEUTRCN A6SCRPTICN CROSS SECTION 

712534 ' 5 0 Co E V 1 5o 0 MEV 25o OX 3 FR 

Jo Yc BARRE 

CAD 

o: 

FOR FAST REACTOR CALCULATIONSc 


40 ZIRCONIUM CAPTURE CROSS SECTIuN 

02-162 5 2So3 MV lo OC KEV SoOX 2 USA GoToCRTON PL 

O: FOR Rc'ACTOR MODERATION AND REACTIVITY EFFECTS; 

6S1142 3o OC KEV 1 Co 0 MEV IScOX 2 USA RccHPLICH KAP 

O: FOR RSACTOR MODERATION AND REACTIVITY FFFECTSo 

TO VERIFY EXISTING MEASUREMENTS FOR NEUTRON 

ENERGIES LESS THAN 25 KEVo 

TO RESOLVE DISCREPANCIES IN EXISTING DATA FROM 

25 KEV TO 1 MEVc 

NO DATA AVAILABLE A60V3 1 MEV; 


STA TUS 

STATUS 

ANL POENITZ - LSNCC-1 8(1972 I. WCRK IN PROGRESS 400 KEV TO 1:5 MEV; 

LRL CZIRR* - LSNDC-1 94(1972), WORK IN PROGRESS 100 EV TO 1 MEVo 

40 ZIRCONIUM NcLTRON NEUTRCN EMISSION CROSS SECTION 

£21223 3 o CO MEV 14oC MEV ICovX 1 USA RcEhRLICH KAP 

CoEOTILL 

ANL 

Q : SECONDARY FNSRGY-ANGLE DISTRIBUTIONS RE QUI REDc 

A: INCIDENT AND EXIT ENERGY RE SOLLTI ON 10 PERCENTo 

0: FOR DESIGN OF PRESSURIZED WATER REACTORS USING ZRc 


40 ZIRCONIUM 90 NEUTRON ANGULAR DIFFERENTIAL INELASTIC CROSS SECTION (CONTINUED) 

STATUS 

STATUS 

KTY MC ELLISTREM* - WORK IN PROGRESS lc5 TO 6 MEVc 

ANL GUENTHIR* - ANL ZNDM—4 (1974), DATA 1=8 TC 4«C MEVc 

40 ZIRCONIUM 9C NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

721561 SoOO MEV 15c 0 MEV lOoOX 1 USA N:STEEN EE T 

o: TO DETERMINE THE SPLIT OF TOTAL ZR CROSS SEC T I0N 

BETWEEN ELASTIC AND INELASTICo 

"0 ZIRCONIUM 90 NEUTRCN RESONANCE PARAMETERS 

651151 1 5o C MEV lOcOX 2 USA Ro EHRLICH KAP 

NoSTEEN 

BET 

0: ELASTIC AND GAMMA WIDTHS WANTEDe 

ENERGY TO INCLUDE LOWEST RESOLVED RESONANCEo 

0: NEEDED TO VERIFY EXISTING MEASUREMENTSo 

DISCREPANCIES STILL EXISTo 

M: SUBSTANTIAL MODIFICATIONSO 

STATUS 

STATUS 

ORL GOODo - 1 1C 4CC KEVo 

40 ZIRCONIUM 9C NEUTRON CAPTURE RESONANCE INTEGRAL 

651150 Oo 50 EV 20e OX 2 USA R;EHRLICH KAP 

0: NEEDED FOR EVALUATING MEASUREMENTS AND 

RESONANCE PARAMETERSo 

40 ZIRCONIUM 91 DISCRETE LEVEL STRUCTURE (ENERGY. SPIN. PARITY) 

651157 2 USA RoEHRLlCH KAP 

O: LEVELS FROM 1,0 Tu 3s 0 MEV WANTEDc 

0: FOR CALCULATING COMPOUND ELASTIC AND INELASTICo 


»0 ZIRCONIUM 91 NEUTRCN TOTAL CRCSS_SEC T ION 

Z52CS2 2o 00 MV 100c EV lOoOX 2 TUK Cc ERTEK CNA 

AoISYAR 

CNA 

0: FOR REACTIVITY EFFECTS MEASUREMENTSo 

M: NEW REOUESTO 

STA TUS 

STATUS 

BRC ADAM* - 7 2KI £Vo 

40 ZIRCONIUM 91 NEUTRCN DIFFERENTIAL ELASTIC CROSS SECTION 

Z21563 1OOo KEV 1Oo 0 MEV lOoOX 1 USA NoSTEEN BET 

Q: SCATTERING FROM SEPARATED ISOTOPES 90-91 . 92-94, 

AND 96 IS DESIRED; 

O: TO CHECK THE SHELL EFFECT ON THE OPTICAL 

POTENT IALc 

TO DERIVE USEFUL OPTICAL MODEL PARAMETERSo 

STATUS 

STATUS 

KTY MC ELL I STREW* - WORK IN PROGRESS lo5 TO 6 MEVo 

40 ZIRCONIUM 91 NEUTRCN ANGULAR DIFFERENTIAL INELASTIC CROSS SECTION 

651153 14o 0 MEV ISoOX 2 USA RoEhRLICH KAP 

Q: RESOLVE DISCRETE LEVELS UP TO 2 MEV EXCITATIONo 

0: TO COMPUTE DIRECT INELASTIC SCATTERING AND 

INVESTIGATE ISOTOPIC SPIN DEPENDENT COUPLING 

BETWEEN GROUND AND EXCITED STATESo 

STATUS 

KTY MC ELLISTREW* - WORK IN FRCGRESS lo5 TO 6 MEVo 

STATUS 

40 ZIRCONIUM 91 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

Z21564 EoOO MEV 1 5o 0 MEV USA NoSTEEN BET 

TO DETERMINE THE SPLIT OF THE 

SECTION BETWEEN ELASTIC AND 

SUBSTANTIAL MODIFICATIONSo 

TOTAL ZR CROSS 

INELASTICo 

4 0 ZIRCONIUM 91 NEUTRCN CAPTURE CROSS SECTION 

Z52051 2o 00 MV 100c EV lOoOX TUK CoERTEK 

AoISYAR 

CNA 

CNA 

O: FOR REACTIVITY EFFECTS MEASUREMENTSo 



40 ZIRCONIUM 91 NÛTRCN N,ALPHA 

.65.1.154 14=0 KEV 30o OX 3 USA RcEh.CLlCH KAP 

40 ZIRCONIUM 91 NEUTRCN RESCNANC z PARAMETERS 

651156 15c 0 KEV 10;0X ; USA RcEHRLICH KAP 

NOS T E:EN 

BET 

Q: ELASTIC AND GAMMA WIDTHS WANTEDo 


0: NEEDED TO RESOLVE DISCREPANCIES BELOW 4 KEV AND 

TO EXTEND RESOLVED RANGE TO 15 KEVo 

M: SUBSTANTIAL MOOI F ICAT IONSo 

STATUS 

STATUS 

ORi- MU GHABGHAS + - LSNDC-! 141(1572), IN FSOGSESSc 

ORL GOODo - 1 TO 4 C C KEVc 

40 ZIRCONIUM 91 NEUTRON CAPTURE RESONANCE INTEGRAL 

651155 Co 50 EV 5c OX 1 USA RcEHRLICH KAP 

0: VERIFICATION OF EXISTING DATA REOUIREOo 

40 ZIRCONIUM 92 DISCRETE LEVEL STRUCTURE (ENERGY, SPIN, PARITY) 

651161 A RcEHRLICH KAP 

0: J ANC PI FOR ALL LEVELS LESS THAN 4 MEV REQUIREDc 

0: FOR CALCULATING COMPOUND ELASTIC AND INELASTICo 

40 ZIRCONIUM 92 NEUTRCN DIFFERENTIAL ELASTIC CROSS SECTION 

Z21C66 ,C0 KEV Nc STEEN BE 

KTY MC ELLISTFEWt - WORK IN PROGRESS lc5 TO £ MEVo 

ANL GUENTHC.P+ - ANL/NDM —4 (1974), DATA 1,8 TO 4o : MEVc 

SCATTERING ON SEPARATED ISOTOPES IS OESIREO TO 

CHECK THE SHELL EFFECT ON THE OPTICAL POTENTIAL 

AND DERIVE USEFUL PARAMETERSo 

SUBSTANTIAL MODIFICATIONS! 

-STATUS 

40 ZIRCONIUM 92 NEUTRON ANGULAR DIFFERENTIAL INELASTIC CROSS SECTION 

651.156 14,0 KEV 1 5c 0 X 2 USA ^cEHRLICH KAP 

Q: RESOLVE DISCRETE LEVELS TO 2 MEV ExclTATIONc 


INVESTIGATE ISOTOPIC SPIN-DEPENDENT COUPLING 


STATUS 

STATUS 

KTY MC ELLISTFEK+ - WC3K IN PRCG=ESS 1 05 TO 6 MEVo 

ANL GLENTHEF+ - ANL/NOM-4 (1 974), DATA 1,8 TO 4C0 MEVc 

4 0 ZIRCONIUM 92 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

221C67 5c 00 K.EV 1 5c C MEV ICoOX 2 USA NoSTEEN BET 

o: TO DETERMINE THE SPLIT OF THE TOTAL ZR CROSS 

SECTION BETWEEN ELASTIC AND INELASTICo 

M: SUBSTANTIAL MOO IFICATI ONSc 

ZIRCONIUM 92 NEUTRON RESONANCE PARAMETERS 

651160 15c 0 MEV lOoOX 1 USA Rc EHPLICH KAP 

NcSTEEN 

BET 

a: NEUTRON AND.CAPTURE WIDTH NEEDEDo 


0: VERIFICATION OF EXISTING DATA REQUIREDo 

STA TUS 

STATUS 

ORL MACKLIN+ - WORK IN PROGRESS, 

GEL o MEASUREMENTS IN PROGRESS TO 30 KEVo 

40 ZIRCONIUM 92 _ NEUTRON CAPTURE RESONANCE INTEGRAL 

651155 Oo 50 EV 20o0X 2 USA RcEHRLICH KAP 

0: NEEDED FOR EVALUATING MEASUREMENTS. AND 

RESONANCE PARAMETERS© 

40 ZIRCONIUM 93 NEUTRCN CAPTURE CROSS SECTION 

ZiliZI 1 c 00 KEV lCcO MEV USA RoEoSCHENTER HED 

0: CALCULATION OF FISSION PRODUCT POISON FOR FAST 

REACTORSc 



"0 ZIRCONIUM 93 _ __N|UTKCN 

CA ? T y??_ CRO S?_55?Ii -!£2-I! NUED ! 

252J04 1CCo EV 4GC; KEV 3Co OX 2 JAP ScI IJ IMA NPG 

HoMATSUNOBU 

SAE 

0: FOR FAST R E AC T OR CALCULATI ONSc 

NO EXPERIMENTAL DATA ABOVE IOC EVo 

M: NEW REQUEST C 

40 ZIRCONIUM 94 DISCRETE LEVEL STRUCTURE (ENEF GY, SPIN. PARITY) 

651163 2 USA Rc EHRLICH KAP 

Q: J AND PI FOR ALL LEVELS LESS THAN 4 MEV REQUIREDc 

o: FOR CALCULATING COMPOUND ELASTIC AND INELASTICo 

40 ZIRCONIUM 94 NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

621538 5o 00 ME V 1 So 0 MEV ICoOX 2 USA NcSTEEN SET 

0: SCATTERING ON SEPARATED ISOTOPES IS DESIRED TO 

CHECK THE SHELL EFFECT ON THE OPTICAL POTENTIAL 

AND DERIVE USEFUL PARAMETERSo 

M: SUBSTANTIAL MODIFICATIONS! 

STA TUS 

STATUS 

KTY MC ELL ISTRE M+ - WORK IN PROGRESS lo 5 TO 6 MEVo 

40 ZIRCONIUM 94 NEUTRON ANGULAR DIFFERENTIAL INELASTIC CROSS SECTION 

621 OSS 14o 0 MEV ISoOX 2 USA Rc EhRLICH KAP 

0: RESOLVE DISCRETE LEVELS UP TO 2 MEV EXCITATIONo 


INVESTIGATE ISOTOPIC SPIN-DEPENDENT COUPLING 


40 ZIRCONIUM 94 NEUTRON __ ENERGY DIFFERENT IAL INELASTIC CROSS SECTI0N__ 

241£22 5c CO MEV 15c 0 MEV lOoCX 2 USA NoSTEEN BET 

o: TO DETERMINE SPLIT OF THE TOTAL ZR CROSS SECTION 

BETWEEN NONELASTIC AND ELASTICo 

M! NEW REQUESTc 


232045 lOcO KEV SoOX 2 FR Ho TELL IER SAC 

O: DETECTORc 

40 ZIRCONIUM 94 NEUTRCN RESCNANCE PARAMETERS 

651162 1 5o 0 MEV lOoOX 

STATUS 

ORL MACKLIN* - WORK IN PROGRESSo 


O: VERIFICATION REQUIRED INCLUDES RECENT RPJ RESULTSc 


621010 loOO EV 10o0 KEV NcSTEEN BET 

o: RADIOACTIVE TARGET, 65 DAYo 

THERMAL CROSS SECTION AND RI WANTEDo 

A: ACCURACY 10 PERCENT IF CROSS SECTION GREATER THAN 

100 BARNS AND 20 PERCENT IF BETWEEN 10 AND 100 

BARNSo 

ENERGIES ABOVE 1 EV OF INTEREST TO GIVE 10 PERCENT 

IN RESONANCE INTEGRAL IF GREATER THAN 1000 

BARNS AND 20 PERCENT IF BETWEEN 100 AND 1 COO 

BARNSo 

o: THE DECAY IS TO AN IMPORTANT FISSION PRODUCTo 


621011 1 Oo 0 KEV RcEHRLlCH KAP 

a: RADIOACTIVE TARGET, 65 OAYo 


A: ACCURACY 10 PERCENT IF CROSS SECTION GREATER THAN 

100 BARNS AND 2C PERCENT IF BETWEEN 10 AND 100 

BARNSo 



BARNS AND 20 PERCENT IF BETWEEN 100 AND 1000 

BARNSo 

O: THE DECAY IS TO AN IMPORTANT FISSION PRODUCTo 


651862 2 5o 3 MV 2 CAN W o He WALKER CRC 

A: ACCURACY REQUIRED 20 BARNSc 

0: FISSION PRODUCT, UNKNOWN CROSS SECTIONo 

241023 1 o 00 KEV 1 Oo 0 MEV 20o0X 2 USA RoEoSCHENTER HED 

O: RADIOACTIVE TARGET. 65o 5 DAYo 

o: CALCULATION OF FISSION PRODUCT POISON FOR FAST 

REACTORSc 



40_ZIRCONIUM_95_ _ NEUTPCN CAPTURE CROSS SECTION (CONTINUED) 

STATUS 

STATUS 

SAC RIBONo - 72BOLCGNA 1 225, REVIEW, 

»C_Z_1RCCNIUM 96 NELTRCN CAPTURE CROSS SECTION 

222Z$6 10=0 KEV 5o0X 2 FR He T ELL IER SAC 

0: DETECTORo 

43_ZIRC0NIUM 96 NEUTPCN RESONANCE PARAMETERS 

ZS10Z4 2C0e EV 10,OX 1 USA ReEHRLICH KAP 

o: NEUTRON AND GAMMA WIDTHS REOUIREDo 

0: NEEDED TO VERIFY MEASUREMENT ON 300 EV RESONANCE 

AND REMOVE DISCREPANCIES© 


STA TUS 

STATUS 

ORL GGOOo - 1 TO 4CC KEVo 

41 NIOBIUM 93 NEUTRCN TOTAL CROSS SECTION 

ZS2090 2o 00 MV 25o 0 MV lOoCX 2 T UK CcERTEK CNA 

AcISYAR 

CNA 

0: FOR REACTIVITY EFFECTS MEASUREMENTSo 

MI NEW REQUESTc 

41 NIOBIUM 93 _ NEUTRON ELASTIC CROSS SECTION 

Z5J.34 J 2So3 MV 20c 0 MEV 3cOX 2 INC Gc Be GARG TRM 

0: REQUIRED =GR STRUCTURAL-MATERIAL CALCULATIONS, 


4i NIOBIUM 93 NEUTRCN INELASTIC CROSS SECTION 

2A212X So 00 MEV ScOX 1 EUR NEUTRON DOSIMETRY GROUP GEL 

o: PRODUCTION OF 3,7 YEAR ISOMER NEEDEDo 

O: PROMISING FAST NEUTRON FLUENCE MONITOR DUE TO LOW 

THRESHOLD ENERGY, 

Z-5-2054 20o 0 MEV 3o C X 2 INC Gc 3c GARG TRM 

O: REQUIRED FOR STRUCTURAL-MATERIAL CALCULATIONSc 


STATUS 

STATUS 

ALD COLES - AWRE/0-C6/71, CATA 1 TC 5 MEVo 

AE ETEMADo - AE-461 ( 1973). DATA 2,0 TO 40 6 MEVc 

N OC SCHETT+ - EANDC-95 (1974 I. COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974, 

41 NIOBIUM 93 NEUTRCN ABSCRPTICN CROSS SECTION 

2X2H31 500= EV 15o 0 MEV 25, OX 3 FR JcY,BARRE CAD 


__ _ NEUTRON CAPTURE CROSS SECTION 

621.04S 1,00 KEV 1OOo KEV lOoOX 2 USA P,Be HEMMIG AEC 

CoEcTILL 

ANL 

o: LOOK FOR NON-l/V BELOW 1 EVo 

A: ACCURACY - 5 PERCENT IN CALCULATED DILUTE AND 

SELF-SHIELDED RESONANCE INTEGRAL© 

O: FOR FAST REACTOR CALCULATIONS. TO RESOLVE 

DISCREPANCIES IN THERMIONIC REACTOR WORTHSc 

662020 1 OOo EV lOCo KEV 20c 0 X 2 UK Cc Gc CAMPBELL WIN 

0: FOR FAST REACTORS: 

Z0201S 50 Go EV 1© 00 MEV 30o0X 3 FR J o Y, BARRE CAD 


242X32 1o 00 EV 10c 0 KEV 5oOX 2 EUR NEUTRON DOSIMETRY GROUP GEL 

0: PRODUCTION OF NB-94 ( 20000 YEARS) WANTED, 

0: POSSIBLE LONG TERM FLUENCE MONITORo 

2S2SQS 2o 00 MV 25o 0 MV lOoOX 2 TUK CoERTEK CNA 

Ac ISYAR 

CNA 

o: FOR REACTIVITY EFFECTS MEASUREMENTSo 


Z53045 2 5© 3 MV 20© 0 MEV 3o0X 2 INC Go Bo GARG TRM 

0: REQUIRED FOR STRUCTURAL-MA TE R I AL CALCULATIONS© 


FISSICN LIST PAGE II, 34

44 R U T H E N I U M 101 NEUTRON CAPTURE CROSS SECTION (CONTINUED) 

STA TUS 

ORi_ 

MACKLINc - (1974), DATA TC 7C0 KEVo 

ANL POENITZo - ANL/NDM-B (1974), DATA Oo3 TO 2o5 MEVo 

STATUS 

HAR CCATES - MEASUREMENT PLANNEOo 

41 NI03JUM 93 NEUTRCN PHOTON PRODUCTION CROSS SECTION IN INELAS T IC SCATo 

6S2155 15o 0 MEV lGeGX 2 SWT Jo 9RUNNER WUR 

0: FORMATION OF THE 3C 7 YEAR ISOMER (E• = 29 KEV)3 

o: FOR FAST FLUX MEASUREMENTSc 

41 NIOBIUM 93 NEUTRCN N, 2N 

74215.3 15c 0 MEV SoOX 2 EUR NEUTRON DOSIMETRY GROUP GEL 


METhODSc 


INTEGRAL AND DIFFERENTIAL MEASUREMENTSc 

STA TUS 

STATUS 

KFK KliSTERSo - ( 1S 7 3) o PRESENT RESULTS OBTAINED EY COUNTING Co93 MEV GAMMA RAYS FROM ZR-92 

FOLLOWING DECAY OF 1Oo 2-DAY NB-92o A 3o 2-HOUR NB-92 ISOMER IS ALSO REPORTED, SYSTEMATICS AND 

STATISTICAL THEORY INDICATE TGC LCW CROSS CROSS SECTION PERHAPS CUE TO UNOBSERVED DECAYo 

HAR BLOWo - JNE 26 9(1972). DISCUSSION CF DISCREPANCY BETWEEN THEORY AND EXPERIMENT, 

NDC SCHETT+ - EANDC-S5 (1974 ). CCMFILATI ON OF EXPERIMENTAL DAT A AVAILABLE AS OF JANUARY 1974o 

ANL SMITH* - ANL/NCM-6 (1974), EVALUATION FROM 12 TC 20 MEVc 

41 NIOBIUM 93 NELTRCN N,F 

21203$ 15o 0 MEV 30c OX 3 FR Jo Yc BARRE CAD 


41 NIOBIUM 93 NEUTRCN N,ALPHA 

Z1203S 1 So 0 MEV 30 o OX 3 FR JoYo BARRE CAD 


4 1 NIOBIUM 95 NEUTRON CAPTURE CROSS SECTION 

611212 RcEhRLICH KAP 

RADIOACTIVE TARGET - 35 Do 

THERMAL AVERAGE WILL BE USEFULo 

WANT 20 PERCENT ACCURACY IF ABSORPTION CROSS 

SECTION IS 10 TO 100 B, 10 PERCENT IF GREATERo 

DECAYS TO AN IMPORTANT FISSION PRODUCT POISON0 

42 MOLYBDENUM ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

221020 1c 50 MEV 3o 00 .MEV 20o OX CcEcTILL 

Po Be HEMMIG 

ANL 

AEC 

0: TOTAL INTEGRAL OVER 4 PI REQUIREDo 


ANISOTROPIC 

A: ENERGY RESOLUTION OF PRIMARY AND SCATTERED 

NEUTRONS 20 PERCENTo 

STATUS 

ALD COLES* - AHRE/0-89/70. DATA FOR 10 LEVELS AND CONTINUUM Is 5 TO 6 MEVc 

ANL SMITH* - ANL/NCM-7. DATA TC 4 MEV FOR EVEN ISOTOPESc 

KTY MC ELLISTREM+ - WCRK UNDERWAY FOR EVEN ISOTOPES TO 6 MEVc 

4 2 MOLYBDENUM NEUTRON ABSORPTION CROSS SECTION 

21.2340 1 So 0 MEV 20 c 0 X FR JoYiBARRE CAD 


42 MOLYBDENUM CAPTURE CROSS SECTION 

6S2151 1OOo EV lo 00 MEV 1 UK CoGcCAMPBELL WIN 

A: ACCURACY 1C PERCENT TO 100 KEV. 20 PERCENT ABOVEc 


202216 500o EV lo 00 MEV 25o OX 2 FR JoYoBARRE CAD 


121012 1o 00 KEV 1o 00 MEV lOoOX 3 USA Po Bo HEMMIG AEC 

0: TO RESOLVE DISCREPANCY IN REACTIVITY WORTH 

MEASUREMENTSo 

FISSION LIST PAGE I lo 35

42 MOL YBDdN UM N5UTRCN CAPTURE CROSS SECTION (CONTINUED) 

STATUS 

STATUS 

ANL POcNITZc - (15 7 4), DATA TC 2c5 MEVc 

HAS COATES - MEASUREMENT PLANNED, 

42_M0L YBCENUM __ NEUTRCN N, F 

6S215S 14o C MEV lCcOX 2 GER FoWELLER KFK 

Z1SSA1 15o 0 MEV 25o C X 2 FR Jc Yc BARRE CAD 

0: FOR FAST REACTOR CALCULATI ONSc 

STATUS 

STATUS 

KFK CIERJACKSo - ( 1573 )c 14-MEV DATA PCI NTS =Cfi MO-92.-94,-56, -97 AND F ISSION-SPECTRUM-AVERA GEO 

DATA ONLY, PRESENT ACCURACY 30 TC 50 PERCENT, 

42 MOLYBDENUM NEUTRCN N,ALPHA 

Z-12 342 15,0 MEV 25c OX 2 Ffi Jc Y,EARRE CAC 


STA TUS 

STATUS 

KFK CIERJACKSo - (1573)o 14-NEV DATA FOR MO-92,-98, -IOC ANC FISSION-SPECTRUM-AVERAGED DATA FCR MG 

ONLYo ESTIMATED ACCURACY 30 TO 50 FERCENTo 

42 MOLYBDENUM 92 NEUTRCN N«F 

£92160 15o 0 MEV lOoOX 3 FR Ac MICHAUDON BRC 

0: PRODUCT ION OF NB-52 ( 10c 1 DA Y)c 


STA TUS 

STATUS 

KYU KANDA - NF/A 165 177(1572). DATA 13 TO 15 MEVc 

GIT F INK* - PR/C 1 356(1970. CATA AT 14,4 MEV, 

NDC SCHETT+ - EANDC-55 (1974 ), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS 0= JANUARY 1974, 

YSDENUM 95_ _ NEUTRCN INELASTJC CROSS SEC T ION 

122£47 15c 5 MEV 50= OX 1 FR J,Y,BARRE CAD 

0: FISSION PRODUCT EFFECT IN FAST REACTORS, 

STATUS ; STATUS 

SAC RIBONo - 73B0LCGNA 1 235, REVIEW, 

42 MOLYBDENUM 95 NEUTRCN CAPTURE CROSS SECTION 

Z2£Z4£ 500c EV 200, KEV 30o OX 2 FR JoY:BARRE CAD 

0: RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE 

TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-236o 

o: FISSION PRODUCT EFFECT IN FAST REACTORSo 

Zf2905 5Oo 0 KEV 40Cc KEV 30o0X 2 JAP So IIJIMA NPG 

HoMATSUNOBU 

SAE 

0: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE 

o: FOR FAST REACTOR CALCULATIONS, 

NO EXPERIMENTAL DATA ABOVE 50 KEVo 


STA TUS 

STATUS 

NPG IIJIMA+ (1S7S). NO EXPERIMENTAL DATA AEOVE 50 KEVo 

42 MOLYBDENUM 95_ NEUTRCN N.F 

692164 15= 0 MEV lOoOX 3 FR AcMICHAUDON ERC 

Q: PRODUCTION OF NB-95 (35 OAY)o 

0: ACTIVATION DETECTOR, 

42 MOLYBDENUM 95 _ NEUTRON CAPTURE_RESONANCE INTEGRAL 

Z410Z5 Co 50 EV 1Oo 0 KEV 1OoOX 2 USA NcSTEEN BET 


42 MOLYBDENUM 96 NEUTRON CAPTURE CROSS SECTION 

£9.-52 0 1 Oo 0 KEV 1 OOo KEV lOoOX 2 AUL J = L, SYMONDS AUA 

0: RESONANCE PARAMETERS AND P-WAVE STRENGTH FUNCTION 

ALSO REQUIREDc 

0: FOR FISSION PRODUCT CALCULATIONS AND ASTROPHYSICSo 


42 MOLYBDENUM 57 NEUTRCN INELASTIC CROSS SECTION 

232545 1 So C MEV SOoOX 1 FR JoYoBARRE CAD 

O: FISSION PRODUCT EFFECT IN FAST REACTORSo 

STATUS 

STATUS 

SAC RIBONo - 7 2EOLCGNA 1 235 , REVIEWc 

42 MOLYBDENUM 97 NEUTRCN CAPTURE CROSS SECTION 

232555 SCOo EV 200o KEV 30o0X 

Ffi JcY:BARRE CAD 

RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE 


FISSION PRODUCT EFFECT IN FAST RcACTORSO 

Z52006 6Co C KEV 4OOo KEV 2Co3X 

ScIIJIMA 

HoMATSUNOBU 

NPG 

SAE 



NO EXPERIMENTAL DATA ABOVE 6? KEVo 

M: NEW REOUESTc 

42 MOLYBDENUM 98 CAPTURE CROSS SECTION 

22265.1 SCOo EV 200o 3Gc OX JcYiEARRE CAD 

O: RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE 


0: FISSION PRODUCT EFFECT IN FAST REACTORSo 

42 MOLYBDENUM 99 CAPTURE CROSS SECTION 

62-1613 1o 00 MV 1O 00 KEV NoSTEEN 

Ro EHRLICH 

BET 

KAP 

o: 

RADIOACTIVE TARGET 66 HOURSo 

WANT 20 PERCENT ACCURACY IF ABSORPTION CROSS 

SECTION.IS 10 TO 100 B, 10 PERCENT IF GREATERo 




BARNSo 

THE DECAY IS TO AN IMPORTANT FISSION PRODUCTo 

651503 25o3 MV 2 CAN WoHcWALKER CRC 

A: ACCURACY REQUIRED 600 Be 

O: FISSION PRODUCT, UNKNOWN CROSS SECTIONo 

43 TECHNETIUM 99 NEUTRCN INELASTIC_CROSS SECTION__ 

232552 15o0 MEV SOoOX 1 Ffi JcY;BARRE CAD 


STATUS 

STATUS 

SAC EVALUATION IN PRCGRcSS

44 RUTHENIUM 101 NEUTRON CAPTURE CROSS SECTION (CONTINUED) 

Z410ZS 1 a OC KEV 10=0 MEV 10c OX A RoEcSCHENTER KEO 


REACTORSc 

M: NEh REQUEST; 

252005 20 c 0 X So I I J IMA 

HoMATSUNOBU 

NPG 

SAE 

Q: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE 


NO EXPERIMENTAL DATA ABOVE 100 EVo 


-STATUS 

SAC RIBONo - 7 2ECLCGNA 1 235. REVlEWo 

NPG I IJIMA+ (1975), NO EXPERIMENTAL DATA ABOVE 50 KEVo 

44 RUTHENIUM 102 NEUTRCN CAPTURE CROSS SECTION 

2.32055 5 COc EV 2Co OX JcYoEARRE . CAD 



FISSION PRODUCT EFFECT IN FAST REACTORSo 

252009 100c EV 30o OX S o 11J IMA 

HoMATSUNOBU 

NPG 

SAE 

a: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE 


NO EXPERIMENTAL DATA EXCEPT 3 DATA POINTS AT 2, 

24 AND 190 KEVo 


-STATUS 

SAC RIBONo - 72B0L CGNA 1 235 , REVIEWo 

NPG IIJIMA+ (1975), EXPERIMENTAL DATA AVAILABLE AT ONLY 3 ENERGIES - 2, 24 AND 190 KEVo 

44 RUTHENIUM 103 CAPTURE CROSS SECTION 

62101.5 loOO MV lo 00 KEV NoSTEEN 

ROEHRLICH 

BET 

KAP 

Q: RADIOACTIVE TARGET 40 DAYSo 

A: 20 PERCENT ACCURACY DESIRED IF CROSS SECTION IN 

RANGE 10 TO 100 BARNS, 10 PERCENT IF LARGERo 

ENERGIES ABOVE 1 EV Or INTEREST TO GIVE 10 PERCENT 



BARNSc 

O: WANTED FOR FISSION PRODUCT POISON CALCULATIONS IN 

THERMAL REACTORSo 

691504 2 So 3 MV N W c He WALKER CRC 


o: FISSION PRODUCT, UNKNOWN CROSS SECTIONo 

241025 loCO KEV 1 Oo 0 MEV RoEcSCHENTER HED 

Q: RADIOACTIVE TARGET 39o6 DAYo 


REACTORSc 


44 RUTHENIUM 104 CAPTURE CROSS SECTION 

222055 5 C Oo E V 200o JoYcBARRE CAD 




241081 

1o 00 

KEV 

1 Oo 0 MEV 

RoEcSCHENTER 

HED 

Q: RADIOACTIVE TARGET 4c35 MINo 


REACTORSc 


252010 

1 OOo EV 

400o 

30 o OX 

So 11J1MA 

HoMATSUNOBU 

NPG 

SAE 

STATUS- 

a: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE 



IIJIMA+ (1S75). THERE ARE 7 CATA POINTS IN THE RANGE 1 KEV TO IE MEV, BUT THE DISCREPANCIES ARE 

REMARKABLE AT 24 KEV AND BETWEEN 14 ANC 15 MEVo 

-STATUS 

44 RUTHENIUM 106 NEUTRON CAPTURE CROSS SECTION 

Z41052 1 o 00 KEV 1Oo 0 MEV RoEoSCHENTER HED 

0: RADIOACTIVE TARGET 2ol8 HOURo 


REACTORSc 



45 RHODIUM CAPTURE CROSS SECTION 

241565 1 o OC MV Io 00 KEV 1 Oo OX 

0: THERMAL CROSS SECTION AND RI WANTEOo 

01 FOR FISSION PRODUCT POISON CALCULATIONSo 


45 RHODIUM 103 INELASTIC CROSS SECTION 

65242.7 1Oo 0 MEV GER McKUECHLE KFK 

0: CROSS SECTION LEADING TO ISOMERIC STATE AFTER 

GAMMA DE-EXCITATION IS WANTEDo 

o: THRESHOLD OETECTORo 

232552 1 5o 0 MEV SOoOX FR JoYoBARRE CAD 


242122 1 Oo 0 MEV SoOX R NEUTRON DOSIMETRY GROUP GEL 

0: PRODUCTION OF 57 MINUTE ISOMER WANTEOo 

O: PROMISING FAST NEUTRON FLUENCE MONITOR DUE TO LOW 

THRESHOLD ENERGYo 

NOC SCHETT+ - EANDC-S5 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974o 

MOL FABRY* - INDC


741.084 1 c 00 KE V 1 Oo 0 MEV 10,OX a Rc E,SCHENTER HED 


REACTORSo 


Z52011 

Sc 11J IMA 

HoMATSUNOBU 

NPG 

SAE 



NO EXPERIMENTAL DATA ABOVE 100 EVo 


STATUS- 

-STATUS 

SAC RIBONo - 72E0LCGNA 1 235. REVlEWo 

ORL MACKLINc - (1574), PRELIMINARY DATA 2,5 TO 500 KEV 

RPI K NO X + - USNOC-11 220( 1574), IN PROGRESS 

46 PALLADIUM 107 NEUTRON CAPTURE CROSS SECTION 

£71.02 0 1 Co OX 

RADIOACTIVE TARGET - 7 MILLION YEARSo 

ABOVE 1 EV WANT RESONANCE INTEGRAL TO 10 PERCENTo 

FOR CALCULATION OF FISSION PRODUCT POISONSo 

£S160£ 2 5o 3 MV N Wo H c WALKER CRC 

A: ACCURACY REOUI RED 15 BARNSo 

0: PU FISSION PRODUCT, UNKNOWN CROSS SECTION© 

Z32££l 5 COc EV Jo Yc BARRE CAD 

Q: RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE 



741004 

lo OC KEV 1 CoOX 

Ro EoSCHENTER 

HED 

0: RADIOACTIVE TARGET - 6c 5 MILLION YEARSo 


REACTORSc 


7=2012 

4 OOo KEV 

So I I J IMA 

HoMATSUNOBU 

NPG 

SAE 



NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo 


-STATUS 

SAC RIBONo -r 7 3EOLCGNA 1 235 , REVIEWo 

NPG IIJIMA+ (1575), NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo 

47 SILVER CAPTURE CROSS SECTION 

752001 lo 0CE-C4 EV 200o SWC HoHAEGGBLOM 


47 SILVER 107 CAPTURE CROSS SECTION 

741065 1c 00 MV 5,00 KEV lOoOX 

o: THERMAL CROSS SECTION AND RI WANTEDo 

O: FOR FISSION PRODUCT POISON CALCULATIONSo 


47 SILVER 107 NEUTRCN N,ALPHA 

£52021 2 5,3 MV 

o: FOR NEUTRON ACTIVATION ANALYSIS AND CROSS SECTION 

SYSTEMATICS WANTEDo 

47 SILVER 109 NEUTRON CAPTURE CROSS SECTION 

£71021 1o 00 MV lo 00 EV lOoOX BoHUTCHINS GEB 

FISSION PRODUCT POISONc 

1.320£2 500c EV 200o KEV 30o OX JoY,BARRE CAD 

O: RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE 


0: FISSION PRODUCT EFFECT IN FAST REACTORS, 

252012 lOOo EV 400, KEV 30,OX SoIIJIMA 

HoMATSUNOBU 

NPG 

SAE 

DES IREO WITH LOWER PRIORITY FOR WIDER ENERGY RANGE 

FOR FAST REACTOR CALCULATIONSo 

NEW REQUESTo 



STATUS 

STATUS 

NPG IIJIMA+ ( 1C7E)o THERE ARE 37 DATA POINTS EELOW 6 MEV. BUT A SYSTEMATIC DISCREPANCY IS OBSERVED 

BETWEEN WESTON'S DATA AND KCNONOV•S DAT Ao 

48 CADMIUM NEUTRON CAPTURE CROSS SECTION 

2£2002 loOOE-C4 EV 2 C Oc EV SoOX 2 SWC Ho HAEGGBLOM AE 


48 CADMIUM 110 NEUTRCN CAPTURE CROSS SECTION 

65J3022 1 Co 0 KEV lOOo KEV 1 Oo OX 2 AUL J = L; SYMONDS AUA 

Q: RESONANCE PARAMETERS AND P WAVE STRENGTH FUNCTION 

ALSO REQUIREDo 

O: FOR FISSION PRODUCT CALCULATIONS AND ASTROPHYSICSo 

48 CADMIUM 113 NEUTRCN CAPTURE CROSS SECTION 

23206; lOOo EV 5 o OX 3 FR Ho TELLIER SAC 

0: CONTROL AND POISON; 

49 INDIUM NEUTRON . ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

202012 4o 00 MEV 7oOC MEV 3 JAP KoNAKAMURA FE 


0: FOR INVESTIGATION OF LEVEL DENSITY PARAMETERSo 

49 INDIUM NEUTRON CAPTURE CROSS SECTION 

2-E2002 lo C0E-C4 EV 20Go EV SoOX 2 SWC Ho HAEGGBLOM AE 


49 INDIUM 11S NEUTRON INELASTIC CROSS SECTION 

652.150 1 So 0 MEV 3c CX 1 GER McKUECHLE KFK 

0: CROSS SECTION LEADING TO ISOMERIC STATE AFTER 

GAMMA DE-EXCITATION IS NEEDEDo 

O: THRESHOLD DETECTORo 

142.116 2 o 0 X 1 EUR NEUTRON DOSIMETRY GROUP GEL 

0: PRODUCTION OF IN-115 (4c 5 HOUR I ISOMERo 

AVERAGE CROSS SECTION IN A U-235 FISSION SPECTRUM 

DESIREDc 

0: FOR NORMALIZATION OF AVERAGE CROSS SECTIONS FOR 

DOSIMETRY PURPOSE Sc 

STATUS 

STATUS 

MOL FABRY* - 7C HELSINKI 2 £35(1970). EVALUATION; 

K TO KOBAYASHI• - JNE 27 741( 1973). DATA 3o4 TO 4o9 MEV 

NDC SCHETT+ - EANDC-55 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974, 

CRC SANTRY+ - 1 SWASH, DATA FRCM Co 3 TG 15 MEVo 

49_INDIUM 115 NEUTRON _PH0T0N PRODUCTION CROSS SECTIONjN INELASTIC SCAT0 

652194 5o 00 MEV 15o 0 MEV 10o(^X 2 SWT Jo BRUNNER WUR 

O: FORMATION OF THE 4o5 HOUR ISOMER (E* = o33S MEVIo 

o: FOR FAST FLUX MEASUREMENTSc 

50_TIN 12£ _ NEUTRON _ CAPTURE CROSS SECTION 

651502 25o 3 MV 2 CAN wo H= WALKER CRC 

A: ACCURACY REQUIRED 120 BARNSo 

O: FISSION PRODUCT. UNKNOWN CROSS SECTIONo 

SI ANTIMONY 121 NEUTRCN N.2N 

242542 15o 0 MEV 20o0X 3 FR Ac M1CHAUDON BRC 

o: FOR ACT IV AT ION o 

51 ANTIMONY 123 NEUTRCN N.2N 

242042 15o 0 MEV 20 o 0 X 3 FR Ao MICHAUDON BRC 

o: FOR ACTIVATIONc 


51 ANTIMONY 125 CAPTURE CROSS SECTION 

6S1606 2 So 3 MV CAN Wo Ho WALKER CRC 



51 ANTIMONY 127 NEUTRON CAPTURE CROSS SECTION 

651605 2 So 3 WV N WoHc WALKER CRC 



52 TELLURIUM 127 CAPTURE CROSS SECTION 

621022 loOO MV lo 00 EV A RoEHRLICH KAP 

o: RADIOACTIVE TARGET 105 DAY ISOMERo 

THERMAL OR THERMAL AVERAGE VALUE USEFULc 

0: NEEDED FOR CALCULATION OF FISSION PRODUCT POISONSo 

651510 N Wo Ho WALKER CRC 

0: FOR THE ISOMERIC STATE (105 0)c 


0: FISSION PRODUCTc 

52 TELLURIUM 129 NEUTRCN CAPTURE CROSS SECTION 

651611 N Wo Ho WALKER CRC 

Q: FOR THE ISOMERIC STATE (33 Die 

A: ACCURACY REQUIREO 1000 BARNSo 

0: FISSION PROOUCTo 

52 TELLURIUM 132 NEUTRON CAPTURE CROSS SECTION 

621023 2 So 3 MV 1 o 00 EV NoSTEEN BET 

Q: 

A: 

RADIOACTIVE TARGET 78 HOUR So 

ACCURACY 1C PERCENT IF CROSS SECTION LARGER THAN 

2500 BARNSo 

ABOVE I EV RESONANCE INTEGRAL WANTED TO 20 PERCENT 

IF BETWEEN 2=00 AND 25000 BARNS AND 10 PERCENT 

IF LARGER THAN 25000 BARNSo 



53 IODINE 127 

242134 1Oo0 MEV 14o 6 MEV SoOX 2 EUR NEUTRON DOSIMETRY GROUP GEL 


METHODSo 

MORE THAN 25 PERCENT DISCREPANCY BETWEEN INTEGRAL 

AND DIFFERENTIAL MEASUREMENTSo 

STATUS 

STATUS 

NOC SCHETT+ - EANCC-55 ( 1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974o 

53 IODINE 129 NEUTRON CAPTURE CROSS sIcTION 

241567 loOO KEV 10o 0 MEV Ro Eo SCHENTER HED 

Q: RADIOACTIVE TARGET - 15c 9 MILLION YEARSo 

O: CALCULATION OF FISSION PRODUCT POISON FOR FAST 

REACTORSo 

M: NEW REQUESTO 

53 IODINE 133 NEUTRON CAPTURE CROSS SECTION 

621024 loOO MV 1o 00 KEV 20o0X NOSTEEN BET 

0: RADIOACTIVE TARGET 21 HOUR So 

A: ACCURACY 1C PERCENT IF CROSS SECTION LARGER THAN 

9000 BARNSo 

ABOVE 1 EV RESONANCE INTEGRAL WANTED TO 20 PERCENT 

IF BETWEEN 9000 AND 90000 BARNS AND 10 PERCENT 

IF LARGER THAN 90000 BARNSo 

0: WANTED FOR FISSION PRODUCT POISON CALCULATIONSo 

54 XENON 131 NEUTRON CAPTURE CROSS SECTION 

621025 loOO MV lo 00 KEV lOoOX 

NcSTEEN 

Bo HUTCH INS 

BET 

GEB 

o: 

M : 

THERMAL CROSS SECTION AND RESONANCE INTEGRAL 

WANTEDo 


ACCURACY IN RESONANCE INTEGRALo 

FISSION PROOUCTo 


232064 lOoO MV SoOO KEV lOoOX FR Ho TELL IER SAC 

0: REACTOR CALCULATIONSo 


54 XENON 131 NEUTRCN CAPTURE CROSS SECTION (CONTINUED) 

752214 1 COc E V 4GOo KEV 20o OX 1 JAP So I IJ IMA NPG 

HoMATSUNOBU 

SAE 

O: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE 




STATUS 

STATUS 

NPG IIJIMA+ (1575). NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo 

54 XENON 133 NEUTRON ' CAPTURE CROSS SECTION 

621222 2So3 MV lOoOX 2 USA ScHUTCHINS GEB 

a: RADIOACTIVE TARGET 5O 3 DAYSo 

THERMAL OR THERMAL AVERAGE VALUE WANTEDo 

o: WANTED FOR FISSION PRODUCT POISON CALCULATIONSo 

212245 lo 00 MV 1o 00 KEV SoOX 3 DEN CoFoHOEJERUP RIS 

o: WANTED FOR FISSION PRODUCT CALCULA TI ON So 

241266 1o 00 MV So 00 KEV 3 o 0 X 2 USA NoSTEEN BET 

a: RADIOACTIVE TARGET - So 25 OA Yo 


WANTEDo 



STATUS 

STATUS 

MCM KENNETT+ - ÎN 5 253(1958). THERMAL VALUEo 

SAC RIBONo - 73B0LCGNA 1 235, EVALUATION FOR THERMAL AND FISSION SPECTRAc 

54 XENON 135 NEUTRCN CAPTURE CROSS SECTION 

62122£ 1o 00 MV 2o 00 EV So OX 2 USA RchcCAHLBERG GA 

a: RADIOACTIVE TARGET 9o 3 HOURSo 

0: FOR DESIGN OF THORIUM CYCLE REACTORSo 

Z 52265 1 Oo 0 MV 5o 00 KEV lOoOX 2 FR HoT ELL IER SAC 

O: REACTOR CALCULATIONSC 

241S8S 1o CO MV So 00 KEV SoOX 1 USA NoSTEEN BET 

O: RADIOACTIVE TARGET - 9c17 HOURo 


WANTED TO 3 PERCENTo 

0: FOR FISSION PRODUCT POISON CALCULATIONSo 


54 XENON 135 NEUTRCN TOTAL PHOTON PRODUCT ION CROSS SECTION 

62122S 2 So 3 MV 2 USA RoEhRLICH KAP 

O: RADIOACTIVE TARGET 9o2 HOURSo 

GAMMA RAY SPECTRA WANTED FOR GAMMA RAY ENERGIES 

BETWEEN 1 AND E MEVo 

A: GAMMA RESOLUTION 10-20 PERCENTo 

o: NEEDED FOR GAMMA SHIELDING AND HEATING 

CALCULATIONSo 

55 CESIUM 133 NEUTRON INELASTIC CROSS SECTION 

222266 1 So 0 MEV SOoOX 1 FR JoYo BARRE CAD 


STATUS 

STATUS 

SAC RIBONo - 73B0LCGNA 1 235. REVIEWo 

55 CESIUM 133 SIuTRON ABSORPTICN CROSS SECTloN 

232S6S SOOo EV 15o 0 MEV 30o OX 2 Ffi CcOEVILLERS SAC 


55CESIUM 133 NEUTRCN CAPTURE CROSS SECTION 

621335 1o00 MV lo 00 KEV lOoOX 1 USA BoHUTCHINS GEB 

Q: THERMAL CROSS SECTION AND RESONANCE INTEGRAL 

WANTEOo 



621231 loOO MV 1o 00 KEV lOoOX 2 USA NoSTEEN BET 

a: THERMAL CROSS SECTION AND RESONANCE INTEGRAL 

WANTEDo 

0: FOR FISSION PRODUCT POISON CALCULATION So 



55 CESIUM 133 NEUTRON CAPTURE CROSS SECTION < CONTINUED) 

61-1352 Oo 50 EV lo 00 KEV lOoOX 1 USA EoHUTCHINS GEB 

NoSTEEN 

BET 

O: FOR CALCULATION OF FISSION PRODUCT POISONSo 

122062 1Oo 0 MV 5o 00 KEV ICoOX 1 FR Ho T ELL IER SAC 

O: BURN UP PHYSICSc 

222065 5 OOo EV 2 OOo KEV ICoOX 1 FR J o Y a BARRE CAD 

o: RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE 



252015 100c EV 4 OOo KEV 20 o 0 X 1 JAP So I IJ IMA NPG 

HoMATSUNOBU 

SAE 




STATUS 

STATUS 

SAC RIBONo - 73B0LCGNA 1 235. REV IEW.THERMAL TC 30 KEV ALSO FISSION NEUTRON SPECTRUM AVERAGEo 

BOR RIGAUD+ - NF/A 176 545(1571), AT 14o0 MEVo 

KFK KOMPE - NP/A 133 513(1965). FROM 10 KEV TO 150 KEV 

WUR WIODER - PRECISE DATA FROM OoOl TC 45 EV. TO BE PUBLISHED IN NSE, 

NPG IIJIMA+ ( 157 5 Io MANY EXPERIMENTAL DATA BELOW 15 MEV, BUT SYSTEMATIC DISCREPANCIES ARE 

OBSERVED ABOVE 10 KEVo 

55 CESIUM 135 NEUTRON CAPTURE CROSS SECTION 

252020 5OOo EV 200o KEV JoYoEARRE CAD 




241090 1o 00 MV 1Oo 0 KEV lOoOX NcSTEEN BET 

RADIOACTIVE TARGET - 3o 3 MILLION YEARSo 


WANTED, 

FOR FISSION PRODUCT POISON CALCULATIONSo 

NEW REQUEST, 

241391 1o 00 KEV 

10o0 MEV lOoOX RoEoSCHENTER HED 

0: RADIOACTIVE TARGET - 3c 3 MILLION YEARSo 


REACTORSc 


252016 1 OOo EV 

So 11J IMA 

HoMATSUNOBU 

NPG 

SAE 





56 BARIUM 136 NEUTRON CAPTURE CROSS SECTION 

653023 1 Oo 0 KEV L JoL,SYMONDS AUA 

0: RESONANCE PARAMETERS ALSO REQUIRED, 

P AND D WAVE STRENGTH FUNCTIONS ALSO NEEDED, 

O: FOR FISSION PRODUCT CALCULATIONS AND ASTROPHYSICS, 

58 CERIUM 144 CAPTURE CROSS SECTION 

241053 1o 00 KEV 10,0 MEV RoEoSCHENTER HED 

O: RADIOACTIVE TARGET - 284 DAYo 


REACTORSo 


59 PRASEODYMIUM 141 CAPTURE CROSS SECTION 

241092 1o 00 MV 

1Oo 0 KEV lOoOX NoSTEEN BET 

0: THERMAL CROSS SECTION AND RESONANCE INTEC 

WANTEDo 


RESOLVE UNCERTAINTIES IN AVAILABLE DATA, 


STATUS- 

DEB 

DEB 

ANL 

ORL 

CSIKAI+ - NF/A 55 229(1968)o 

PETO+ - JNE 21 757(1967), 

STUPEGIAt - JNE 22 267(1568)o 

MACKLIN+ - (1574), PRELIMINARY DATA 2o5 TC 500 KEV 


59 PRASEODYMIUM 1 41 RESCNANCE PARAMETERS 

6S2214 So 0 0 KEV 

0: 

A: 

PARTIAL RADIATION WIDTHS NEEDEDo 

ACCURACY REQUIRED TO BETTER THAN IS PERCENTo 

60 NEODYMIUM 143 CAPTURE CROSS SECTION 

621534 1o 00 KEV lOoOX NcSTEEN 

B o HUT C HIN S 

BET 

GEB 

o: 

M: 


WANTED: 

ENERGIES ABOVE lot EV OF INTEREST TO GIVE 10 

PERCENT IN RESONANCE INTEGRALo 



732571 1Oo 0 MV So 00 KEV lOoOX FR HoTELLIER SAC 

0: BURN UP PHYSICSc 

232522 500= EV 200o KEV lOoOX FR JoY:BARRE CAD 

O: BURN UP PHYSICSo 

252512 lOOo EV 

400o KEV 20 o 0 X SclIJIMA 

HcMATSUNOSU 

NPG 

SAE 





STATUS- 

-STATUS 

SAC RIBONo - 73BOLCGNA 1 235, EVALUATION FROM 0o025 EV TO i0 KEVo ALSO FISSION NEUTRON SPECTRUM AVERAGE 

HAR CABELL* - JIN 30 857(1568)o PILE SPECTRA AVERAGESo 

NPG IIJIMA+ - < 1 57= >c NO EXPERIMENTAL DATA BETWEEN 100 EV AND 400 KEVo 

60 NEODYMIUM 1 45 NEUTRCN CAPTURE CROSS SECTION 

671036 1o 00 MV lo 00 KEV ICoOX 1 USA NoSTEEN BET 

BcHUTCHINS 

GEB 

Ro EHRLICH 

KAP 

O: THERMAL CROSS SECTION AND RESONANCE INTEGRAL 

WANTEOo 

A: ENERGIES ABOVE 1oC EV OF INTEREST TO GIVE 10 

PERCENT IN RESONANCE iNTEGRALo 

0: FOR CALCULATION OF FISSION PRODUCT POISONSo 


252523 1Oo 0 MV So 00 KEV lOoOX 1 FR HoTELLIER SAC 

0: BURN UP STUDY: 

252524 SCOo EV 200o KEV lOoOX 2 FR Jo Y c BARRE CAD 

o: BURN UP STUDY: 

241094 1o 00 KEV lOcO MEV lOoOX 1 USA Ro Ec SCHENTER HED 


REACTORSc 


252016 1 COo EV 400o KEV 20o OX 1 JAP So I IJ IMA NPG 

HoMATSUNOBU 

SAE 





STATUS 

STATUS 

SAC RIBONo - 72B0LCGNA 1 235. EVALUATION FROM 0oC2S EV TO 30 KEVc ALSO FISSION NEUTRON SPECTRUM AVERAGE 

HAR CABELL+ - ÎN 30 857(1568)o PILE SPECTRA AVERAGES 

ORL MACKLIN+ - (1574). PRELIMINARY DATA 2c 5 TO 500 KEV 

60 NEODYMIUM 146 NELTRCN CAPTURE CROSS sIcTION 

252525 SCOo EV 200o KEV 20o 0 X 2 FR JoYcEARRE CAD 

O: BURN UP STUDY, 

STATUS 

STATUS 

SAC RIBONo - 72BOLCGNA 1 235. EVALUATION FRCM 0o025 EV TO 30 KEVc 

OSL AL STAD+ - JIN 29 2155(1967 >o THERMAL VALUEo 


60 NEODYMIUM 147 CAPTURE CROSS SECTION 

62-1035 loOO MV lo 00 KEV RcEHRLICH 

NoSTEEN 

Bo HUTCHINS 

KAP 

BET 

GEB 

0: RADIOACTIVE TARGET, 11 OAYSo 


WANTEDo 

A: ACCURACY 20 PERCENT IF ABSORPTION CROSS SECTION 

IN RANGE 10 TO 1 CO BARNS, 10 PERCENT IF BETWEEN 

1 CO AND 1000 BARNS AND 5 PERCENT IF LARGERo 

ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE 

INTEGRAL TO 20 PERCENT IF BETWEEN 100 AND 1000 

BARNS, 10 PERCENT IF 1000 TO 10000 BARNS AND 

5 PERCENT IF LARGERo 


651512 2 So 3 MV N W o Ho WALKER CRC 

A: REQUIRED WITH 350 BARN ACCURAC Yc 

O: FISSION PRODUCT WITH UNKNOWN CROSS SECTIONo 

212046 1o 00 MV lo 00 KEV SoOX N CoFoHOEJERUP RIS 

0: WANTED FOR FISSION PRODUCT CALCULATIONSo 

222026 lOoO MV 5o CO KEV lOoOX 1 FR HoTELLIER SAC 

0: BURN UP PHYSICSo 

SO NEODYMIUM 148__ NEUTRCN CAPTURE CROSS SECTION 

2.22022 5C0c EV 200o KEV 20o0X 2 FR JoY:BARRE CAD 

O: BURN UP STUDY, 

STATUS 

STATUS 

OSL ALSTAD+ - JIN 25 2155(1967lo 

MUA HASAN+ - NC/B 58 402C 1 S68)o 

61 PROMETHIUM 147 NEUTRON CAPTURE CROSS SECTION 

621542 lo 00 MV 1o 00 KEV lOoOX 1 USA NcSTEEN 

BoHUTCHINS 

BET 

GEB 

RADIOACTIVE TARGET - 2o 6 YEAR, 

WANT TOTAL AND (N,GAMMA I FOR FORMATION OF PM-148 

AND THE PM-148 ISOMERo 


WANTEOo 

ENERGIES ABOVE IcO EV OF INTEREST TO GIVE 10 


NEEDED FOR CALCULATION OF FISSION PRODUCT POISONSo 

SUBSTANTIAL MOO IFICATIONSo 

21204.7 loOO MV lo 00 KEV DEN CcFoHOEJERUP RIS 

O: WANTED FOR FISSION PRODUCT CALCULATIONSc 

222025 500o EV 200o KEV 20o0X 1 FR JoYo BARRE CAD 

a: RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE 



252015 1OOo EV 400o KEV 20o0X 1 JAP So I IJ IMA NPG 

HoMATSUNOBU 

SAE 





STATUS 

STATUS 

MTR COCDING+ - NSE 43 58(1971). RESONANCE PARAMETERSo 

SAC RIBONo - 73EOLCGNA 1 235. REVIEWo 

NPG IIJIMA+ (1575). NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo 

61 PROMETHIUM 146 NEUTRCN CAPTURE CROSS SECTION 

621J044 lo 00 MV 1o 00 KEV NcSTEEN 

BoHUTCHINS 

BET 

GEB 

RADIOACTIVE TARGET - 41 DAY ISOMERo 


ENERGIES ABOVE loC EV OF INTEREST TO GIVE 10 




621046 1 o 00 MV lo 00 KEV lOoOX USA NoSTEEN 

BoHUTCHINS 

RoEHRLICH 

BET 

GEB 

KAP 

RADIOACTIVE TARGET - 5o 3 7 DA Yc 


LOOK FOR 1/V ABOVE 1 EVc 

FOR FISSION PRODUCT POISON CALCULATIONSo 


6S1S13 5, 00 EV 20o 0 X Wo Ho WALKER CRC 

FOR THE ISOMERIC STATE (42 D)o 

AOOITIONAL DATA NEEDED TO DETERMINE DEPENDENCE ON 

NEUTRON TEMPERATURE AND EPI THERMAL FLUXo 

FISSION LIST PAGE IIo 46

61 PROMETHIUM 145 NEUTRCN CAPTURE CROSS SECTION 

6J124S 1o 00 MV loOO KEV 20o0X 1 USA NoSTEEN BET 

Bo HUTCH INS 

GEB 

Ro EHRLICH 

KAP 

RADIOACTIVE TARGET - 53 HOURc 


ACCURACY 10 PERCENT WANTED IF CROSS SECTION 

GREATER THAN 10CC BARNS. 20 PERCENT IF BETWEEN 

15 AND 1000 BARNSo 


INTEGRAL TO 10 PERCENT IF GREATER THAN 10000 

BARNS OR 20 PERCENT IF BETWEEN 1000 AND 10000 

BARNSo 



621552 1o00 MV lo 00 KEV lOoOX 2 USA NoSTEEN BET 

Bo HUTCH INS 

GEB 

0: RADIOACTIVE TARGET 28 HOURo 

THERMAL CROSS SECTION AND RI WANTEDO 

A: ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE 

INTEGRAL TO 10 PERCENTo 

o: FOR CALCULATION OF FISSION PRODUCT POISONSo 


62 SAMARIUM NEUTRCN RESCNANCE PARAMETERS 

6S2235 200o EV 3 ITY VoBENZI 80L 

0: PARTIAL RADIATION WIDTHS NEEDEDc 

A: ACCURACY REQUIRED TO BETTER THAN IS PERCENTo 

62 SAMARIUM 144 NEUTRCN N.2N 

&S3S24 14o 0 MEV lOoOX 3 HUN JoCSIKAI KOS 


0: NEEDED FOR NEUTRON ACTIVATION ANALYSIS AND CROSS 


STATUS 

STATUS 

AUB GH0RA1+ - NF/A 223 118(1974), DATA 14o9 TO 17o0 MEVo 

62 SAMARIUM 147 NEUTRCN CAPTURE CROSS SECTION 

25252S SCOo EV 200o KEV 20o0X JoYoEARRE CAD 




62 SAMARIUM 149 CAPTURE CROSS SECTION 

H2Q&B 1 o 00 MV 1 o 00 KEV SoOX 3 DEN Co Fc kOEJERUP RIS 

0: WANTED FOR FISSION PRODUCT CALCULATIONSo 

232560 1Oo0 MV 5o 00 KEV lOoOX 2 FR HoTELLIER SAC 

0: REACTOR CALCULAT IONSo 

252561 SOOo EV 200o KEV 20o0X 1 FR JoYoBARRE CAD 




241595 loOO KEV 1Oo 0 MEV lOoOX 1 USA RoEoSCHENTER HED 


REACTORSc 


252525 1 00© EV 400o KEV 20o0X 1 JAP SoIIJIMA NPG 

HoMATSUNOBU 

SAE 



NO EXPERIMENTAL DATA EXCEPT A MEASUREMENT AT 

30 KEVo 


STATUS 

STATUS 



621552 1o00 MV lo 00 KEV 1 USA NoSTEEN BET 

BoHUTCHINS 

GEB 

0: THERMAL CROSS SECTION AND RI WANTEDo 



INTEGRAL TO BETWEEN 2 AND 3 PERCENTo 





621354 lo 00 KEV NcSTEEN 

So HUTCH IN S 

BET 

GEB 

RADIOACTIVE TARGET - 93 YEARSo 


DESIRED ENERGY RESOLUTION 5 PERCENTo 



WANTED FOR CALCULATION OF FISSION PRODUCT POISONSo 


232082 lOoO MV 5o 00 KEV FR Ho T ELL IER SAC 

O: REACTOR CALCULATIONS, 

252063 SCOo EV J o Yc BARRE CAD 




241356 

1o 00 

KEV 

10c 0 

MEV 

Ro Ec SCHENTER 

HED 

0: RADIOACTIVE TARGET - 93 YEARSo 


REACTORSo 


2S2S21 

100c 

EV 

30 o 0 X 

So I I J IMA 

HoMATSUNOBU 

NPG 

SAE 



NO EXPERIMENTAL DATA FROM ICO EV TO 400 KEVo 


-STATUS 


NPG IIJ1MA+ (1575) , NO EXPERIMENTAL DATA FRCM 100 EV TO 400 KEVo 


£71055 lo 00 KEV NoSTEEN 

BoHUTCHINS 

BET 

GEB 




FISSION PRODUCT POISONo 


-STATUS 

DEB 

MUA 

ORL 

HAR 

PETO + - JNE 21 757(1567). AT 3o0 MEV RELATIVE TC GOLD CAPTURE, 15 PERCENT ERRORo 

CHAUBY+ - FR 1=2 105511966), AT 24o KEV RELATIVE TO INDIUM CAPTURE, 10 PERCENT ERRORo 

MACKLIN - NAT 157 370(19631. AY 30 KEV TC 17 PERCENTo 

CABELL - JIN 24 745(1562). THERMAL VALUco 


£21061 1c 00 MV lo 00 KEV NoSTEEN BET 

RADIOACTIVE TARGET - 47 HOURSo 


ACCURACY OF 10 PERCENT REQUIRED IF CROSS SECTION 

GREATER THAN 30000 BARNS. 20 PERCENT IF LOWERo 



BARNS OR 10 PERCENT IF LARGERo 



£21362 lo CO . MV lo 00 KEV RoEHRLICH KAP 

RADIOACTIVE TARGET - 47 HOURSo 

ACCURACY OF 10 PERCENT REQUIRED IF CROSS SECTION 

GREATER THAN 30000 BARNS. 20 PERCENT IF LOWERo 



BARNS OR 10 PERCENT IF LARGERo 


NEW REQUESTc 

£21614 2 5o 3 MV M W o Ho WALKER CRC 

A: REQUIRED WITH A 10000 BARN ACCURACY, 

0: FISSION PRODUCT WITH UNKNOWN CROSS SECTIONo 

63 EUROPIUM NEUTRON TOTAL CROSS SECTION 

£52252 1Oo 0 KEV 

2o 00 

MEV 

5oOX 

FoWELLER 

241052 loOO EV 

15o 0 

MEV 

ISoOX 

BoHUTCHINS 

Po Bo HEMMIG 

GEB 

AEC 

0: NEEDED FOR RESONANCE SELF-SHI ELD I NGo 


FISSION LIST PAGE I I, AS

63 EUROPIUM NEUTRCN DIFFERENTIAL ELASTIC CROSS SECTION 

652254 1 00c KEV 1Oo 0 MEV lOoOX 3 GER FcWELLER KFK 

6 3 EUROPIUM NEUTRCN INELASTIC CROSS SECTION 

652255 3 Oo C KEV lOoO MEV 20o0X 3 GER FoWELLER KFK 

652252 3 Co 0 KEV 2o 00 MEV 20oCX 3 GER FoWELLER KFK 

O: MEASUREMENT OF INELASTIC SCATTERING TO GROUPS OF 

LEVELS REQUIR EOc 

63 EUROPIUM NEUTRCN ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

652256 2o 00 MEV 1Oo0 MEV 20o OX 3 GER FoWELLER KFK 

63 EUROPIUM NEUTRCN CAPTURE CROSS SECTION 

652255 2 00c KEV 2o 00 MEV lOoOX 2 GER FoWELLER KFK 

252111 lOCo EV SOOo KEV lOcOX 1 UK C c Go CAMPBELL WIN 

0 : FOR FAST REACTORS: 

STA TUS 

HAR MOXONo - (1574)• SOME DATA AVAILABLE, FURTHER WORK IN PROGRESSc 

KFK CHOU+ - JNE 27 Ell(1973), DATA 1 EV TO SO KEVo 

63 EUROPIUM 1 51 NEUTRCN CAPTURE CROSS SECTION 

655025 1o 00 (/V 1 Oo 0 EV SoOX 2 DDR DoALEERT ROS 

0 : CROSS SECTION DATA NEEDED FOR EVALUATION OF 

MEASURED ACTIVATION RATES BY MEANS OF FOILS 

(ESPECIALLY SPECTRAL INDICES) FOR THERMAL 

NEUTRON FLUXESo 

653326 lo 00 EV SoOX 2 BUL Vc CHRISTOV BAC 

0 : FOR ACTIVATION DETECTORS FOR THERMAL NEUTRON FLUX 

DETERMINATIONc 

232364 25o3 MV 5o 00 KEV SoOX 3 FR HoTELLIER SAC 

0 : REACTOR CALCULATIONS, 

241395 1o 00 KEV 1o 00 MEV 5o OX 1 USA Po Be HEMMIG AEC 

M : NEW REQUESTc 

241102 loOO KEV lo 00 MEV lOoOX 2 USA Po Be HEMMIG AEC 

FoGoPEREY 

ORL 

STATUS 

MOL POORTMANS+ - NF/A 172 485( 1971 ), DATA o02 TO o65 EVo 

NPL RVVES - JNE 25 129(1970), THERMAL VALUEo 

LRL CZIRR+ - UCRL-50804 (1570). DATA 200 EV TO 12 KEV 

LRL NETHAWAYo - NF/A 160 635(1572), DATA NEAR 14 MEVo 

RPI KNCX+ - USNDC-11 220(1574). IN PROGRESS 20 EV TO 100 KEVc 

WUR WIDOEK - PRECIEE DATA FRCW OoOl TC 1o5 EV. TO BE PUBLISHED IN NSEo 

0 : RATIO GROUND STATE TO ISOMER CAPTURE WANTEDo 

M : NEW REQUEST, 

63 EUROPIUM 151 NEUTRON CAPTURE GAMMA RAY SPECTRUM 

241100 loOO KEV 1o 00 MEV lOcOX 2 USA Pe Be HEMMIG AEC 

FoGoPEREY 

ORL 

M : NEW REQUESTo 

63 EUROPIUM 151 NEUTRCN RESONANCE PARAMETERS 

652260 20o 0 EV 200o EV lOoOX 2 GER FoWELLER KFK 

0 : NEUTRON AND CAPTURE WIDTH NEEDEDo 

STATUS 

COL RAHN+ - PR/C 6 251(1972), PARAMETERS FROM Oo 32 TO 99 EVo 

63 EUROPIUM 151 NEUTRON CAPTURE RESONANCE INTEGRAL 

653322 2 So 3 MV lOo 0 KEV SoOX 2 DDR OcALBERT ROS 

0 : CROSS SECTION DATA NEEDED FOR EVALUATION OF 





63 EUROPIUM 151 NEUTPCN CAPTURE RESONANCE INTEGRAL (CONTINUED) 

6S2Q2S VoCHRISTOV BAC 

O: FOR ACTIVATION DETECTORS FOR THERMAL NEUTRON FLUX 

DETERMI NATIONo 

63 EUROPIUM 153 NEUTRCN CAPTURE CROSS SECTION 

6Z1C64 loCO MV 1,00 KEV Bo HUT CHINS GEB 

A: ACCURACY OF 2 PERCENT NEAR THERMAL AND 5 PERCENT 

ABOVEo 

ENERGIES ABOVE 1 EV OF INTEREST TO GIVE 

RESONANCE INTEGRAL TO 10 PERCENT, 

O: FOR CALCULATION OF FISSION PRODUCT POISON, 

2220S2 1,00 EV 5,00 KEV FR He TELL IER SAC 


Z.411Q3 5o 00 KEV 1 0,0* A NoSTEEN BET 

0: THERMAL CROSS SECTION AND RI WANTEDo 



7311OS 1 o 00 KEV 1o 00 MEV 1 USA Po Be HEMMIG 


Z52022 4Oo 0 KEV 400o 30,0* So I IJ IMA 

HoMATSUNOBU 

NPG 

SAE 



NO EXPERIMENTAL DATA FROM 40 KEV TO 400 KEVo 


-STATUS 

RPI 

LAS 

DUB 

WUR 

KNCX + - USNDC-11 220(1574), IN PROGRESS 20 EV TO 100 KEV, 

HARLOW* - teWASHINGTON P,837(1968), 25 EV TO 10KEV 

KCNKS+ - SNP 7 313(19681, 1 EV TO 50 KEV, 

WIDOER - PRECISE DATA FROM OoOl TO 10 EV. TO BE PUBLISHED IN NSE, 

ERROR AT THERMAL 15 PERCENT, AT LEAST 8 PERCENT IN REST OF ENERGY RANGE, 

63 EUROPIUM 153 NEUTRCN CAPTURE GAMMA RAY SPECTRUM 

Z31106 1,00 KEV 1,00 MEV 2 USA Po Bo hEMMIG 

Fo G;PER EY 

AEC 

ORL 

63 EUROPIUM 153 NEUTRCN 

RESCNANCE 


PARAMETERS 

£52262 25o 0 EV 200o GER FoWELLER KFK 

a: NEUTRON AND CAPTURE WIDTH NEEDED, 

o: FISSION PRODUCT IMPORTANT IN FAST REACTOR BURNUP 

CALCULATIONSo 

63 EUROPIUM 154 CAPTURE CROSS SECTION 

£21£££ 1 o 00 MV 1 o 00 KEV lOoOX 2 USA NoSTEEN BET 

BoHUTCHINS 

GEB 

0: RADIOACTIVE TARGET - 8o 6 YEARSo 


RESONANCE PARAMETERS WANTED, 



O: FOR CALCULATION OF FISSION PRODUCT POISONS, 


STATUS 

STATUS 

ANL HAYDEN+ - PR 7= 1500(1949), THERMAL VALUE WITH 15 PERCENT ERROR, 

63 EUROPIUM 155 NEUTRON CAPTURE CROSS SECTION 

631Q6H 1,00 MV 1,00 KEV 1 OoOX NoSTEEN 

BoHUTCHINS 

BET 

GEB 

RADIOACTIVE TARGET - 4c8 YEARSo 

THERMAL CROSS SECTION AND RI WANTED, 

RESONANCE PARAMETERS NEEDED, 





Z12050 1o 00 MV 1,00 KEV 5o 0 X CoFoHOEJERUP RIS 

WANTED FOR FISSION PRODUCT CALCULATI ONSo- 

73110a 1,00 KEV 10, 0 MEV 20o0X RoEoSCHENTER HED 

Q: RADIOACTIVE TARGET - 4o 8 YEARSo 

0: CALCULATIONS OF FISSION PRODUCT POISON FOR FAST 

REACTORS, 


FISSION LIST PAGE 11, 50


651515 2 So 3 MV 3 CAN Wo Ho WALKER CRC 

A: REQUIREO WITH A TOO BARN ACCURACYO 

o: FISSION PRODUCT WITH UNKNOWN CROSS SECTIONo 

64 GADOLINIUM NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

621570 1o 50 MEV 1Oo 0 MEV ICoOX 1 USA EchUTCHINS GEB 

STATUS 

ST AT US 

USA USNDCo BELIEVES THAT AVAILABILITY CF ISOTGFIC SAMPLES WOULD MAKE MEASUREMENTS MORE ATTRACTIVEc 

64GAD0LINIUM NEUTRON NEUTRON EMISSION CROSS SECTION 

6J15Z1 1o 50 MEV 1Oo 0 MEV 1SoOX 1 USA BoHUTCHINS GEB 

0: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REQUIREDo 

A: INCIDENT AND EXIT RESOLUTION IS PERCENTo 

0: FOR DESIGN OF THERMAL REACTORS HAVING APPRECIABLE 

QUANTITIES OF GDo 

64 GADOLINIUM NEUTRCN CAPTURE RESONANCE INTEGRAL 

651160 Co SO EV SoOX 1 USA BoHUTCHINS GEB 

0: FOR EVALUATING RESONANCE PARAMETERSo 

64 GADOLINIUM 15S NEUTPCN CAPTURE CROSS SECTION 

621022 Oo 50 EV lo 00 KEV SoOX 1 USA Bo hUTCHINS GEB 



0: NEEDED TO DEFINE NEGATIVE ENERGY RESONANCE IN 

EITHER GD-155 OR GD-157o 


2 J 2066 1 Co 0 MV 5o 00 KEV SoOX 2 FR HoTELLIER SAC 

O: CONSUMABLE POISONo 

242021 1Oo 0 KEV 2 SWO HoHAEGGBLOM AE 

A: ACCURACY 3 PERCENT TO 10 EV, 10 PERCENT ABOVEo 

0: THERMAL REACTOR CALCULATIONSo 

64 GADOLINIUM 155 NEUTRCN RESONANCE PARAMETERS 

651162 SOOo EV lOoOX 1 USA BoHUTCHINS GEB 

0: NEUTRON AND CAPTURE WIDTH NEEDEDo 

MINIMUM ENERGY MUST INCLUDE LOWEST RESOLVED 

RESONANCE, 

o: REQUIRED TO VERIFY EXISTING MEASUREMENTSo 

64 GADOLINIUM 155 NEUTRCN CAPTURE RESONANCE INTEGRAL 

651161 0=50 EV SoOX Bo HUTCHINS GEB 

O: ENERGY REQUESTED IS A MINIMUM VALUE ONLYo 

O: FOR EVALUATING RESONANCE PARAMETERSo 

NEEDED TO DEFINE NEGATIVE ENERGY RESONANCE IN 

EITHER GD-155 OR GO-157o 


64 GADOLINIUM 156 NEUTRON CAPTURE CROSS SECTION 

621523 1O 00 MV loOO KEV A BoHUTCHINS GEB 



0: FOR CALCULATING OF BURN UP IN THERMAL REACTORSo 

64 GADOLINIUM I 56 NEUTRCN RESONANCE PARAMETERS 

651162 2o 00 KEV BoHUTCHINS GEB 


MINIMUM ENERGY TO INCLUDE LOWEST RESOLVED 

RESONANCEo 

0: REQUIRED TO VERIFY EXISTING MEASUREMENTSo 

64 GADOLINIUM 156 NEUTRCN CAPTURE RESONANCE INTEGRAL 

651255 Oo 50 EV 5OCX 1 USA BoHUTCHINS GEB 

o: FOR EVALUATING RESONANCE PARAMETERSo 



6 7-1074 CO 50 EV 1o 00 KEV 5oOX A Eo HUTCHINS GEB 


INTEGRAL TO 5 PERCENTc 

0: FOR CALCULATION 0= BURN UP IN THERMAL REACTORSo 

2-12051 1 o 00 MV 1o 00 KEV 5oOX N CoFoHOEJERUP RIS 

0: * ANTED FOR FISSION PRODUCT CALCULATIONSo 

222052 1Oo 0 MV 5o 00 KEV So OX Ho T ELL I ER S 

0: CONSUMABLE POISONc 

242003 10o0 KEV SWD HoHAEGGBLOM AE 

A: ACCURACY 3 PERCENT TO 10 EV. 10 PERCENT ABOVEo 

O: THERMAL REACTOR CALCULATIONSo 

6A GADOLINIUM 157 NEUTRCN RESONANCE PARAMETERS 

631.155 lo 00 KEV lOoOX BoHUTCHINS GEB 

0: NEUTRON AND CAPTURE WIDTH NEEDEDc 

MINIMUM ENERGY TO INCLUDE LOWEST RESOLVED 

RESONANCEo 

O: REQUIRED TO VERIFY EXISTING MEASUREMENTSo 

64 GADOLINIUM 1 57 CAPTURE RESONANCE INTEGRAL 

651184 0o50 EV 5o OX USA BoHUTCHINS GEB 

0: FOR EVALUATING RESONANCE PARAMETERSo 

64 GADOLINIUM 1 58 NEUTRON RESONANCE PARAMETERS 

241105 2o 00 KEV Eo HUTCH INS GEB 

a: ELASTIC AND GAMMA WIDTH WANTEDo 


0: TO VERIFY'-EXISTING MEASUREMENTSo 


64 GADOLINIUM 160 RESONANCE PARAMETERS 

241110 2o00 KEV BOHUTCHINS GEB 

O: ELASTIC AND GAMMA WIDTH WANTEDo 


0: TO VERIFY EXISTING MEASUREMENTSo 


66 DYSPROSIUM 161 NEUTRON RESONANCE PARAMETERS 

652283 200c EV 3 ITY Vc BENZI BOL 

0: PARTIAL RADIATION WIDTHS NEEOEOo 


66 DYSPROSIUM 164 NEUTRCN " CAPTURE CROSS SECTION 

655025 1o 00 MV 1Oo 0 EV 5o0X 2 DOR Do ALBERT ROS 

o: CROSS SECTION DATA NEEDED FOR EVALUATION OF 




STATUS 

STATUS 

WUR BRUNNER - FRECISE DATA ON NATURAL CY FROM o01 TO 10 EV TO BE PUBLISHED IN NSEo 

BNL COLE+ - USNDC-11 35(1974), MEASUREMENTS FRCM THERMAL TO 140 EVo DATA FOR RESONANCE GAMMAS OF 

EVEN ISOTCPESo 

COL LIOU+ - USNDC-11 65(1974), RESONANCE PARAMETERS FOR DY-162 AND DY-164o 

68 ERBIUM NEUTRCN RESONANCE PARAMETERS 

652286 2 OOo EV 3 ITY VoBENZI BOL 

Q: PARTIAL RADIATION WIDTHS NEEDEDo 


68 ERBIUM 167 NEUTRON CAPTURE CROSS SECTION 

241135 2o 00 EV 3o0X 2 USA RoHcOAHLBERG 

Q : ENERGY REQUESTED IS A MAXIMUM VALUE ONLYo 

0: NEEDED FOR BURNABLE POISON IN TRIGA REACTORSo 



68 ERBIUM 168 NEUTRCN N«ALPHA 

£55030 2 So 3 MV lOoOX 3 HUN JoCSIKAI KOS 

0: FOR NEUTRON ACTIVATION ANALYSIS AND CROSS SECTION 


69 THULIUM 169 NEUTRCN CAPTURE CROSS SECTION 

£52265 loOO KEV 15o 0 MEV lOoOX 1 FR Ac MICHAUDON BRC 

0: PRODUCTION OF TM-170 ( 1 3C DA Y ) c 

0: ACTIVATION DETECTORc 

STA TUS 

STATUS 

OSL ALSTAD+ - INDC(NOR)-l 1(1972). THERMAL AVERAGEo 

69 THULIUM 169_ _ NEUTRCN N.F 

£52250 15o 0 MEV lOoOX 1 FR Ac MICHAUDON BRC 

O: PRODUCTION OF ER-169 ( 9c 4 DA Y) o 

O: ACTIVATION DETECTORc 

69_THULIUM 169 "" NEUTRCN N,ALPHA 

£52251 1 So 0 MEV lOoOX 2 FR Ac MICHAUDON BRC 

0: PRODUCTION OF HO-166 (27 HOUR)c 

O: ACTIVATION DETECTORc 

70 YTTERBIUM 168 NEUTRON CAPTURE CROSS SECTION 

652522 1o 00 EV SoOX 2 BUL VoCHRISTOV SAC 

O: FOR ACTIVATION DETECTORS FOR THERMAL NEUTRON FLUX 

DETERMI NATIONc 

70YTTERBIUM 168_ NEUTRON_ __ CAPTURE RESONANCE INTEGRAL 

653531 1o 00 EV SoOX 2 BUL VoCHRISTOV BAC 

0: FOR ACTIVATION DETECTORS FOR THERMAL NEUTRON FLUX 

DETERMINATION© 

71 LUTETIUM 175 NEUTRON CAPTURE CROSS SECTION 

66253J 1o 00 KEV 1o 00 MEV 20o OX 3 FR Ac MICHAUDON BRC 

O: PRODUCTION OF LU-176 ( 3C THO USAND-MI LL I ON YEARS) 

AND LU-176M ( 2c 7 HOURSIo 


DISCREPANCY AT 10 KEV (2o5 AND 7 B)o 

692294 SoOO MV 250o EV 2 SWT Jc BRUNNER WUR 

A: ACCURACY 2 PERCENT AT THERMAL. 5 PERCENT ABOVEo 

0: NEUTRON THERMOMETERo 

STATUS 

STATUS 

CAS PUBINI+ - NC/A 6 748(1972). THERMAL AVERAGE VALUEo 

MTR YOUNG - BNL-5C276 89(1970). THERMAL AVERAGE VALUEo 

WUR BRUNNER - PRECISE DATA FROM o01 TC 10 EV TC EE PUBLISHED IN NSEo 

COL LI0U+ - PR/C 11 1231(1975). RESONANCE PARAMETERS FROM TRANSMISSION. CAPTURE AND SELF-1NDICAT I ON 

MEASUREMENTSo CATA 1 EV TC 3 KEVo 

71_(_UTeTIUM_17S NEUTRCN N.2N 

662036 1 5o 0 MEV lOoOX 3 FR Ao MI CHAUDON BRC 

O: PRODUCTION OF LU-174 (165 DAY)o 


STA TUS 

STATUS 

JUL OA I Mo - NP/A 224 319(1974). TOTAL ANC ISCMERIC CATA AT 14o7 MEVo 

BRC FREHAUT+ - CEA-R-4627 (1974), DATA THRESHOLD TO 15 MEVo 

71 LUTETIUM_176_ NEUTRON CAPTURE CROSS SECTION 

£62535 1o 00 KEV 3o00 MEV 20o0X 3 FR Ac MICHAUDON BRC 

O: PRODUCTION OF LU-177 ( 6c 2 DA Y) o 


692236 SoOO MV 250o EV 2 SWT JoBRUNNER WUR 

0: ACTIVATION IS REOUIREDo 

A: ACCURACY 2 PERCENT THERMAL. 5 PERCENT ABOVEo 

0: NEUTRON THERMOMETERo 

633533 loOO EV SoOX 2 BUL VoCHRISTOV BAC 

0: FOR ACTIVATION DETECTORS FOR THERMAL NEUTRON FLUX 

DETERMINA TIONo 


71 LUTETIUM 176 NEUTPCN CAPTURE CROSS SECTION (CONTINUED) 

fiaaaat 10o0 EV CoALBERT ROS 

STATUS 

CROSS SECTION DATA NEEDED FOR EVALUATION OF 




MTR YOUNG - BNL-50276 

WUR BRUNNER - PRECISE 

B9(1S7C ) . 

DATA 

FRCM 

THERMAL AVERAGE VALUEo 

oOl TO 2 EV TO BE PUBLISHED IN NSEc 

71 LUTETIUM 176 NEUTRON N, 2N 

652535 1 So 0 MEV lOoOX 3 FR A o MICHAUDON BRC 

71 LUTETIUM 176 NEUTRCN CAPTURE RESONANCE INTEGRAL 

65.3034 2 So 3 MV 1 Oo 0 KEV Do ALBERT ROS 

CROSS SECTION DATA NEEDED FOR EVALUATION OF 




653035 lo 00 EV VoCHRISTOV BAC 

FOR ACTIVATION DETECTORS FOR THERMAL NEUTRON FLUX 

OETERMI NATIONo 

72 HAFNIUM DIFFERENTIAL ELASTIC CROSS SECTION 

661536 

ISoO MEV lOoOX USA NoSTEEN BET 

ACCURACY IN AVERAGE (1-COS) 10 PERCENTo 

ENERGY RESOLUTION - 10 PERCENTo 

WANTED FOR THERMAL REACTOR DESIGNo 


STA TUS- 

AE 

ANL 

HOLMQVIST+ - AE 430 (197C)o 

SHERWOOD* - NSE 39 67(1969), DATA TO loS MEVo 

72 HAFNIUM CAPTURE CROSS SECTION 

621524 loOO MV loOO EV 2o OX NoSTEEN 

Ro EHRLICH 

BET 

KAP 

NEEDED FOR MONTE CARLO CALCULATIONS OF BURNUP IN 

THERMAL REACTORSo 

72 HAFNIUM NEUTRON NEUTRON EMISSION CROSS SECTION 

661532 loOO EV 1 So 0 MEV ISoOX NoSTEEN BET 

0: SECONDARY ENERGY DISTRIBUTION REOUIREOo 

A: INCIDENT AND EXIT ENERGY RESOLUTIONS IS PERCENTo 

o: FOR DESIGN OF THERMAL REACTORS HAVING APPRECIABLE 

QUANTITIES OF HFo 


72 HAFNIUM 174 NEUTRON CAPTURE CROSS SECTION 

661536 1o 00 MV So 00 KEV Ro EHRLICH KAP 

THERMAL VALUE WANTED TO 20 PERCENTo 

NEED AVERAGE P-WAVE CAPTURE WIDTH TO 20 PERCENTo 

BETWEEN 10 AND 100 EV, TOTAL. NEUTRON AND CAPTURE 

WIDTHS NEEDED WITH 10 PERCENT ACCURACYo 

ABOVE 100 EV. 20 PERCENT ACCURACY REQUIREDo 

NEEDED FOR MONTE CARLO BURN UP CALCULATIONSo 

72 HAFNIUM 1 76 CAPTURE CROSS SECTION 

621526 lo 00 MV So 00 KEV NoSTEEN 

RoEHRLICH 

BET 

KAP 

THERMAL VALUE WANTED TO 20 PERCENTo 

BELOW 1 EV, 40 PERCENT ACCURACY NEEDEDo 

BETWEEN 10 AND 100 EV, TOTAL. NEUTRON AND CAPTUF 

WIDTHS NEEDED WITH 10.PERCENT ACCURACYo 


AVERAGE P-WAVE CAPTURE WIDTH TO 20 PERCENTo 

S-WAVE STRENGTH FUNCTION TO 40 PERCENTo 

TO RESOLVE DISCREPANCIES IN RESONANCE INTEGRALo 



232056 1Oo 0 MV So 00 KEV lOoOX 

FR HoTELLIER SAC 

O: REACTOR CALCULATIONSo 

STATUS 

SAC RIBONo - 72B0LCGNA 1 235. PEVIEWo 


72 HAFNIUM 177 NEUTRCN CAPTURE CROSS SECTION 

6211126 So 00 KEV NoSTEEN 

RoEHRLICH 

BET 

KAP 

A." S-WAVE STRENGTH FUNCTION TO 20 PERCENTo 

NEED AVERAGE P-WAVE CAPTURE WIDTH TO 20 PERCENTo 

BELOW 1 EV, 4 PERCENT ACCURACY NEEOEDo 



ABOVE 100 EV, 20 PERCENT ACCURACY REOUIREOo 

5o 39, 6o57» AND 8c 87 EV RESONANCE WIDTHS 5 PERCENTo 

0: TO RESOLVE DISCREPANCIES IN RESONANCE INTEGRALo 



692202 lOoC MV So 00 KEV SoOX 1 FR Ho T ELL IER SAC 

0: RESONANCE INTEGRAL ALSO WANTEDo 

A: ACCURACY 1 PERCENT AT THERMAL AND 5 PERCENT FOR 

RESONANCE INTEGRALo 

O: EVALUATION MAY SUFFICE IF IT EXPLAINS 

01SCR EPANClESo 

STATUS 

STATUS 

SAC RIBONo - 73E0LCGNA 1 235, PEVIEWo PRCBABLY DOES NOT MEET ACCURACY REQUIREMENTSo 

72 HAFNIUM 178 NEUTRCN CAPTURE CROSS SECTION 

£21030 lo 00 MV SoOO KEV NoSTEEN 

RoEHRLICH 

BET 

KAP 

BELOW 1 EV, 5 PERCENT ACCURACY NEEDEDo 

BETWEEN 10 AND 100 EV, TOTAL, NEUTRON AND CAPTUf 


ABOVE 100 EV, 20 PERCENT ACCURACY REOUIREDo 

7o78-EV RESONANCE WIDTH TO 3 PERCENTo 


P-WAVE AVERAGE CAPTURE WIDTH TO 20 PERCENTo 




£92304 1 Oo 0 MV 

STATUS- 

5o CO KEV SoOX HoT ELL I ER SAC 

Q: RESONANCE INTEGRAL ALSO WANTEDo 


RESONANCE INTEGRALO 


DISCREPANCIE S c 

SAC RIBONo - 72EOLCGNA 1 235, REVIEWo FRCBA6LY COES NOT MEET ACCURACY REQUIREMENTS© 

72 HAFNIUM 179 CAPTURE CROSS SECTION 

£21032 1o 00 SoOO KEV NoSTEEN 

RoEHRLICH 

BET 

KAP 

A: BELOW 1 EV, 5 PERCENT ACCURACY NEEDEDo 



ABOVE 100 EV, 20 PERCENT ACCURACY REQUIRED© 

5o 68-EV RESONANCE WIDTHS TO 5 PERCENT© 



0: TO RESOLVE DISCREPANCIES IN RESONANCE INTEGRALo 


M: SUBSTANTIAL MODIFICATIONS© 

6S2.3Q5 1 Oo 0 MV 5© 00 KEV SoOX 1 FR Ho TELL I ER SAC 



RESONANCE INTEGRALo 

o: EVALUATION MAY SUFFICE IF IT EXPLAINS 

DISCREPANCIES© 

STATUS 

STATUS 

SAC RIBONo - 73EOLCGNA 1 235, REVIEW© PROBABLY COES NOT MEET ACCURACY REQUIREMENTSo 

72 HAFNIUM 180 NEUTRON CAPTURE CROSS SECTION 

£711160 1o 00 MV SoOO KEV NoSTEEN 

RoEHRLICH 

BET 

KAP 

BELOW 1 EV, 4 PERCENT ACCURACY NEEOEDo 

BETWEEN 10 AND 100 EV, TOTAL, NEUTRON AND CAPTURE 








752069 lOoO 

5o 00 KEV SoOX FR Ho TELL IER SAC 


STATUS — 

SAC RIBONo - 72B0LCGNA 1 235, REVIEWo PROBABLY COES NOT MEET ACCURACY REQUIREMENTS© 

-STATUS 


73 TANTALUM 181 NEUTRCN CAPTURE CROSS SECTION 

£51155 1o 00 EV SOOo KEV 2 USA PoBohEMMIG AEC 

A: ACCURACY - 1 EV TO 1 KEV. 10 PERCENT, 

- 1 KEV TO 150 KEV, 5 PERCENT, 

- 150 KEV TO 500 KEV, 10 PERCENTo 

DOUBLE ACCURACY USEFULc 

0: FAST BREEDER CONTROL AND BURN-UP CALCULATIONSo 


STATUS 

STATUS 

AE hELLSTROM - JNE 27 71(1573). DATA 30 KEV TC lo5 MEVc 

USP LEPINE+ - NF/A 156 83(1572), DATA 30 TO 300 KEVo 

RPI BLOCK+ - USNOC-3 164(1572). WORK IN PROGRESSc \ 

LRL CZIRR+ - LSNDC-l 54(1972), WORK IN PROGRESSo 

ANL POENITZo - PRELIMINARY DATA Oo5 TO 3 MEVo 

ORL MACKLINo - PRELIMINARY DATA 2o5 TC SCO KEVo 

WUR WI ODER - PRECISE DATA FOR NATURAL TA FROM OoOl TO 20 EV TO BE PUBLISHED IN NSEo 

73 TANTALUM 181 NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION 

I J l J i l 1 c 00 EV 16c 0 MEV 1 Sc OX 2 USA Pc Be HEMMIG AEC 

Q: GAMMA RAYS BELOW 1 MEV IMPORTANTo 


STATUS 

STATUS 

ORL MORGAN* - CRNL-TM-3702 (1572). DATA AT 90 AND 120 DEGREES UP TO 20 MEVc 

ANC GREENWOOD - DATA AT 2 KEVo 

LRL STELTSo - DATA TO 100 KEVo 

74 TUNGSTEN NEUTRCN DIFFERENTIAL ELASTIC CROSS SECTION 

Z42S46 IcOC KEV 15o 0 MEV 10 c OX 1 FR AcMICHAUOON BRC 

o: FOR CRITICAL A SSEMBLIE So 

74 TUNGSTEN NEUTRON DOUBLE CIFFERENTIAL INELASTIC CROSS SECTION 

742247 15o0 MEV lOoOX 1 FR Ac MICHAUDON BRC 

0: FOR CRITICAL ASSEMBLlESc 

74 TUNGSTEN NEUTRON CAPTURE CROSS SECTION 

742245 loOO KEV 3o00 MEV lOoOX 1 FR AOMICHAUDON BRC 

O: FOR CRITICAL ASSEMBLlESc 

74 TUNGSTEN NEUTRON NEUTRCN EMISSION CROSS SECTION 

661240 4 o 00 MEV 16o 0 MEV SoOX 2 USA CoEcCLIFFORD ORL 

STATUS 

JUL OAIMo - NF/A 242 317(1974). DATA AT 14o7 MEV FOR ENRICHED ISOTOPESo 

SECONDARY ENERGY-ANGLE DISTRIBUTIONS REQUIREDo 

LOW ENERGY NEUTRONS SHOULD BE INCLUDEDo 

SPECTRA AT A FEW ANGLES MAY SUFFICEo 

ANGULAR RESOLUTION - 10 DEGREESo 

OUTGOING ENERGY RESOLUTION - 500 KEVo 

ENERGY RESOLUTION 5 PERCENTo 

SUBSTANTIAL MOO IF ICATION So 

74 TUNGSTEN 182 NEUTRON CAPTURE CROSS SECTION 

651202 1c 00 KEV 1Oo 0 MEV lOoOX 2 USA PoBohEMMIG AEC 

0: FAST BREEDER CONTROL AND BURNUP CALCULATIONSo 


STATUS 

STATUS 

ANL POENITZo - PRELIMINARY DATAo 

74 TUNGSTEN 182 NEUTRCN N.2N 

632506 15o 0 MEV 20o0X 1 FR AoMICHAUDON BRC 

Q: PRODUCTION OF W-181 (140 DAY)o 


STATUS • STATUS 

JUL QAIMo - NP/A 242 317(1575). DATA AT 14o7 MEV FOR ENRICHED ISOTOPESo 


7 4 TUNGSTEN 182 NEUTRCN N,ALPHA 

£S5040 2 5o 3 MV lOoOX 5 HUN JoCSIKAI KOS 

O: FOR NEUTRON ACTIVATION ANALYSIS AND CROSS SECTION 


STA TUS 

STATUS 

JUL OA I Mo - NF/A 242 317

77 IRIDIUM 191 NEUTRCN N , 2N 

Z420 50 ISoO MEV lOoOX 1 FR AoMICHAUDON BRC 

o: FOR ACTIVATI ON o 

77 IRIDIUM 193 NEUTRCN CAPTURE CROSS SECTION 

742053 loOO KEV 3o CO MEV 20c OX 2 FR Ac MICHAUDON BRC 

0: FOR ACTIVATIONo 

77 IRIDIUM 193 NEUTRCN N, 2N 

Z42S52 ISoC MEV lOoOX 1 FR AcMICHAUDON BRC 

0: FOR ACT IVATIONO 

78 PLATINUM NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

Z42254 1o 00 KEV 1 So 0 MEV lOoOX 1 FR AoMICHAUDON BRC 

78 PLATINLM NEUTRCN DCUELE DIFFERENTIAL INELASTIC CROSS SECTION 

742055 1 5o 0 MEV lOoOX 1 FR AoMICHAUDON BRC 

78 PLATINUM NEUTRCN CAPTURE CROSS SECTION 

742055 loOG KEV 3o 00 MEV lOoCX 1 FR AoMICHAUDON BRC 

78 PLATINUM NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

Z42056 Io 00 KEV 1 5o 0 MEV 20o0X 2 FR AcMICHAUDON SRC 

78 PLATINLM NEUTRCN N» 2 N 

Z42 0 57 1 5c 0 MEV LOOOX 1 FR AoMICHAUDON BRC 

78 PLATINUM 190 NEUTRCN N, F 

Z4265S 1 5o 0 MEV 20 c 0 X 2 FR AoMICHAUDON BRC 

0: FOR ACT IVAT IONo 

78 PLATINUM 192 NEUTRCN N, F 

Z42060 15o 0 MEV 20o OX 2 FR AoMICHAUDON BRC 

0: FOR ACT IV AT IONo 

7 8 PLATINUM 198 NEUTRCN CAPTURE CROSS SECTION 

Z42061 IcOO KEV 3o00 MEV 20o OX 2 FR Ao MICHAUOON BRC 

0: FOR ACTIVATIONo 

79 GOLD 197 NEUTRCN DIFFERENTIAL ELASTIC CROSS SECTION 

Z42062 loOO KEV 15o0 MEV lOoOX 1 FR Ac MICHAUOON BRC 

79 GOLD 197 NEUTRON DOUELE CIFFERENTIAL INELASTIC CROSS SECTION 

Z42065 1 So 0 MEV lOoOX 1 FR AoMICHAUDON BRC 

79 GOLD 197 NEUTRON CAPTURE CROSS SECTION 

6ZMFL2 Co 50 E V lo 00 KEV loOX 2 USA NoSTEEN BET 

0: INDIVIDUAL AND AVERAGE RESONANCE PARAMETERS 

REOUIREDo 

A: ENERGIES ABOVE Co 5 EV WANTED SO AS TO GIVE 

INFINITE DILUTION RESONANCE INTEGRAL TO 

1 PERCENTc 

0: FOR USE AS A STANDARDo 

662041 1Oo 0 KEV 3o 00 MEV 3o 0 X 1 BLG Ao FABRY MOL 

0: DETECTOR APPLICATIONSo 

65231Z 1.00 KEV 3o 00 MEV lOoOX 1 FR AoMICHAUDON BRC 

0: PRODUCTION OF AU-198 (2c 7 OAYlo 



54 XENON 131 NEUTRCN CAPTURE CROSS SECTION (CONTINUED) 

Z21Q22 lOoC KEV lo OC MEV 2o OX 2 USA RoSoCASWELL NBS 

0: REQUIRED AS PRIMARY STANDARDo 

STA TUS 

STATUS 

RPI BLOCK - LSNDC-3 144(15721, IN PROGRESS TO 80 KEVo 

CAD FORT* - 72VIENNA 239, ACTIVATION METHOD, PRELIMINARY DATA 115 TO 498 KEVo 

CAO LE RIGOLEUF+ - CEA-N-1662(1973), PROMPT CAPTURE GAMMA DETECTION, DATA 75 TO 550 KEVo ANALYSIS OF 

LOWER-ENERGY CATA IN PROGRESS, 

AE HELLSTROM - JNE 27 71 ( 1973). DATA 30 KEV To lo 5 MEVo 

LRL CZIRR* - NSE 52 299(1973), DATA 167 EV TO 600 KEVo 

GEL LISKIEN+ - EANCC(E)-l57(1973). PRELIMINARY DATA 200 KEV TO 3 MEVo 

ORL MACKLIN+ - PR/C 11 1270(1975). DATA 3 TO 550 KEVc 

ANL POENITZ - CATA 400 TO 3500 KEV. TO BE PUBLISHECc 

BNL CHRIEN+ - 7SWASH, MEASUREMENT AT 24 KEVo 

79 GOLD 197 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

£5.3042 3 BZL LoOc B,AGHINA I EN 

Q: GAMMA SPECTRA BETWEEN RESONANCES WANTEDo 


CAPTUREo 

79 GOLD 197 NEUTRON RESONANCE PARAMETERS 

£52341 2o 00 KEV 3 BZL L0O0 BoAGHINA IEN 

O: SPECIAL INTEREST IN THE RATIO OF S WAVE STRENGTH 

FUNCTIONS S( J= 1 )/S< J = 2 ) AND ITS VARIATION AS A 

FUNCTION OF THE ENERGY INTERVALo 

80 MERCURY 198 NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION 

£5304-3 3 BZL Lo Oo Bo AGH IN A I EN 

a: GAMMA SPECTRA BETWEEN RESONANCES WANTEOo 


CAPTUREo 

80_MERCURY 200 NEUTRON _ TOTAL PHOTON PRODUCT ION_CROSS SECTION 

£52044 3 BZL L0O0 Bo AGHINA IEN 



CAPTUREo 

80MERCURY 201 NEUTRON _ TOTAL fÔTON PRODUCTION_CROSS SECTION 

£52045 3 BZL L 0O0 Bo AGHINA IEN 


0: SPECIAL INTEREST ON INTERFERENCE AND DIRECT 

CAPTUREo 

81 THALLIUM 20 3 NEUTRCN CAPTURE CROSS SECTION 

££2044 1o 00 KEV 3o 00 MEV lOoOX 1 FR Ao MICHAUDON BRC 

O: PRODUCTION OF TL-204 ( 3 YEAR ) o 


81 THALLIUM 20 3 NEUTRCN N.2N 

££2042 15o 0 MEV lOoOX 1 FR Ao MICHAUDON BRC 

O: PRODUCTION OF TL-202 ( 12 DAY >0 


81 THALLIUM 204 NEUTRON CAPTURE CROSS SECTION 

£-51005 2=0 3 MV lOoOX 2 USA Go Tc ORTON RL 

O: RADIOACTIVE TARGET - 3c 8 YEARo 

0: WANTED TO TEST FEASIBILITY OF TL-204 PRODUCTIONO 

81 THALLIUM 205 ~ NEUTRON CAPTURE CROSSSECTION 

6£204£ 1o 00 KEV 3o 00 MEV lOoOX 1 FR AoMlCHAUDON BRC 

0: PRODUCTION OF TL-206 (4o2 MINUTElo 


STA TUS 

STATUS 

ORL EARLS* - USNOC-11 197(1974). RESONANCE PARAMETERSo 


81 THALLIUM 20 5 NEUTRGN 

1 5o C MEV Ao MICHAUDON 

0: PRODUCTION OF TL-204 ( 3 YEAR )o 


NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION 

652515 1o 00 KEV 1 6o 0 MEV lOoOX Co DEVILLERS SAC 

0: GAMMA SPECTRA REOUIREOo 

A: NEUTRON AND GAMMA ENERGY RESOLUTION 500 KEVo 

O: FOR SHIELDING CALCULATIONo 


DATA, 

NEUTRCN NEUTRON EMISSION CROSS SECTION 

651005 2o00 MEV 16o 0 MEV USA Co Eo CLIFFORD ORL 

0: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REQUIREDo 

652 316 500C KEV 1 6o 0 MEV lOoOX Co DEVILLERS SAC 

Q: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REQUIREOo 

ENERGY STEP - 500 KEV(INCIDENT NEUTRONSIo 

A: ENERGY RESOLUTION - 250 KEV( EMITTED NEUTRONS) 

0: FOR SHIELDING CALCULATIONo 



88 RADIUM 226 NEUTRCN CAPTURE CROSS SECTION 

752093 0 o 30 EV 1 Oo 0 KEV AoFAERY MOL 

Q: RESONANCE PARAMETERS ALSO WANTEOo 

VALUE OF

90 THORIUM 232 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION (CONTINUED^ 

STATUS 

STATUS 

FEI ZHURAVLEV+ - 71 KIEV, DATA AT 9„2 MEVo 

FOA HOLMBERG+ - NF/A 127 149(1969), DATA 1 TO 2o 2 MEVo 

SUN MC MLRRY+ - INCC(SAF)-4 5(1972), IN FROGRESSc 

ANL SMITH+ - WORK IN PROGRESS TO 4o 0 MEVo 

90 THORILM 232 NEUTRON CAPTURE CROSS SECTION 

621534 1 o 00 MV 5o 00 KEV NoSTEEN BET 

CAPTURE SHAPE IMPORTANT IN KEV RANGE 

ACCURACY REQUIRED - BELOW 2 EV. 2 PERCENTo 

ABOVE 2 EV. 5 PERCENT 

NEED LESS THAN 5 PERCENT IN RESONANCE INTEGRAL BUT 

10 PERCENT IS USEFULc 

FOR THERMAL BREEDER CALCULATIONSo 


652 32.S lo 00 KEV lo 00 MEV UK Co Go CAMPBELL WIN 


652230 4o 00 KEV lOoO MEV GER HoGERWIN JUL 

A: ACCURACY 5 PERCENT TO 2 MEV AND 10 PERCENT ABOVEc 

222090 25o 3 MV 2o 0 % 3 

Ho T ELL IER 

241204 1 Oo 0 KEV 15o 0 MEV 3oOX 1 

USA 

WoOAVEY 

0: NEEDED FOR ASSESSMENT OF U-233/THORIUM REACTOR 

POTENT IALo 


253004 25o 3 MV 20o 0 MEV SoOX 

C Go Be GAR G TRM 

0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo 


FE I 

CCP 

COL 

LRL 

ORL 

ORL 

CHELNOKOV+ - YFI-13 6(1972). DATA 200 EV TO 35 KEVo 

STAVISKY+ - AE 31 107(1970). RELATIVE TO AUo 

RAHN+ - PR/C 6 1654(1972)0 

LINDNER* - LCRL —75838. DATA Oo12 TU 2o 9 MEVo 

HALPERINo - CATA 20 TO 120.EVo 

HALPERINo - WORK IN PROGRESS 2o5 TO 500 KEVo 

90 THORILM 232 NEUTRON N, 2N 

£211362 10o0 MEV 1OoOX 1 USA EoHUTCHINS GEB 

0: NEEDED FOR CONTROL OF U-232 PROOUCTIONo 

692325 1 Oo 0 MEV 20 o OX 3 GER HoGERWIN JUL 

Q: SECONDARY ENERGY DISTRIBUTION REQUIREOo 

90 THORIUM 232 NEUTRON FISSICN CROSS SECTION 

652526 25o3 MV 1Oo 0 MEV GER HcGERWIN JUL 

o: SPECTRUM INDEXo 

232091 1 OOo KEV 1 Oo 0 MEV lOoOX 3 

Ho TELL IER 

241205 15o 0 MEV 3c 0 X 2 

WoDAVEY 

LAS 

Q: RATIO TO U-235 FISSION PREFERREDo 

O: NEEDED FOR ASSESSMENT OF U-233/TH0RIUM REACTOR 

POTENTIAL, 


242135 lo 50 MEV 7o 20 MEV EUR NEUTRON DOSIMETRY GROUP 

o: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING 

METHOOSo 



253305 

2 So 3 MV 20o 0 MEV SoOX D Go Bo GARG TRM 



STATUS- 

STATUS- 

-STATUS 

SOR 

I AE 

NDC 

BEN-DAVID - IAEA-107 57 (1968). REVIEW TO 14 MEVo 

BAKt - KNS 3 77 (1971 ), EVALUAT I ONo 

SCHETT+ - EANDC-95 (1974), COMPILATION OF EXPERIMENTAL_DAT A AVAILABLE ASOF JANUARY 1974o 


50 THORIUM 232 RESONANCE PARAMETERS 

652525 60 00 KEV lOoOX 1 GER HoGERWIN JUL 

0: RADIATION WIDTH NEEDEDc 

212055 1 Co 0 EV 1 Co 0 KEV SoCX 3 FR JoYc EARRE CAD 


-STATUS 

COL 

SAC 

RAHN* - CGC-217E 4 (1572)o 

RIBON+ - 71 KNCXVILLE 438. EVALUATION 

50 THORILM 233 TOTAL CROSS SECTION 

255006 2 Eo 3 MV 20o 0 MEV So OX INC Gc Eo GARG TRM 



90 THORILM 233 ELASTIC CROSS SECTION 

255002 2 Eo 3 MV 20o 0 MEV INC Go Ec GARG TRM 

0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESc 


90 THORIUM 233 NEUTRON INELASTIC CROSS SECTION 

255005 20o 0 MEV SoOX INC Go Bo GARG TRM 



90 THORIUM 233 NEUTRON CAPTURE CROSS SECTION 

25500.9 2 So 3 MV 20o 0 MEV IND Gc Bo GARG TRM 



90 THORIUM 233 FISSION CROSS SECTION 

255010 2 So 3 MV 20o 0 MEV INC Gc Be GARG TRM 



91 PROTACTINIUM 231 NEUTRCN CAPTURE CROSS SECTION 

6S121S 2 So 3 MV 1Oo 0 MEV lOoOX USA EcHUTCHlNS GEB 

0: NEEDED FOR CONTROL OF U-232 PRODUCTION, 

91 PROTACTINIUM 233 NEUTRCN TOTAL CRCSS SECTION 

255011 2 Eo 3 MV 2Oo 0 MEV SoOX INC GcBo GARG TRM 

O: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESc 


91 PROTACTINIUM 233 ELASTIC CROSS SECTION 

255012 2 Eo 3 MV 20o 0 MEV INC Gc Be GARG TRM 



91 PROTACTINIUM 233 NEUTRCN INELASTIC CROSS SECTION 

255012 20o 0 MEV INC Gc Be GARG TRM 

O: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo 


51 PROTACTINIUM 253 NEUTPCN ABSORPTION CROSS SECTION 

652535 2Eo 3 MV 

SOOo 

EV 

SoOX 1 GEfi MAERKL SRE 

652485 2So 3 MV 

SOOo 

EV 

So OX 3 NED MoEoAcHERMANS VDN 

91 PROTACTINIUM 233 

NEUTRCN 


671065 loOO MV 1,00 KEV USA Ro H,DAHLBERG GA 

A: ACCURACY 5 PERCENT BELOW 2 EV, 10 PERCENT ABOVEc 

O: DESIGN OF THORIUM CYCLE REACTORSo 

FISSION LIST PAGE I I, 62

91 PROTACTINIUM 233 NEUTRCN CAPTURE CROSS SECTION < CONTINUED) 

£51221 1o 00 MV 100c EV ICoOX 2 USA AoMoPERRY ORL 

o: THORIUM CYCLE DESIGN So 

.755213 25o 3 MV 20o 0 MEV SoOX 2 INC Gc EoGARG 

T RM 



STATUS 

STATUS 

BET C CNN ER - WAPO-TM-837 ( 1970). THERMAL VALUE, 

91 PROTACTINIUM 223 NEUTRCN FISSION CROSS SECTION 

755515 25o3 MV 20o 0 MEV SoOX 2 INC Go Ec GARG TRM 



91 PROTACTINIUM 233 NEUTRON RESONANCE PARAMETERS 

652232 1OOo EV lOoOX 3 NEC MiEc Ao HERMANS VON 


91 PROTACTINIUM 233 NEUTRON ABSORPTION RESONANCE INTEGRAL 

£52333 Oo 50 EV ICoOX 1 GER MAERKL SRE 

STATUS 

STATUS 

BET CONNER - kAPD-TM-837 (1970)o 

91 PROTACTINIUM £24 NEUTRON TOTAL CRCSS SECTION 

252015 25o 3 MV 20o 0 MEV SoOX 2 INC Go Eo GARG TRM 



91 PROTACTINIUM 224 NEUTRCN ELASTIC CROSS SECTION 

253012 2 Eo 3 MV 20o 0 MEV SoOX 2 INO Ge Be GARG TRM 

o: REQUIRED FOR THORIUM FUEL-CYCLE STUDIES, 


91 PR0TACTINIUM_234 NEUTRON _ INELASTIC CROSS SECTION 

252015 20o 0 MEV SoOX 2 INO Go Bo GARG TRM 



91 PROTACTINIUM 234 NEUTRON CAPTURE CROSS SECTION 

253015 2 Eo 3 MV 2 Oo 0 MEV SoOX 2 INC Go Bo GARG TRM 



91 PROTACTINIUM 234 NEUTRCN FISSICN CROSS SECTION 

252020 2 5o 3 MV 20o 0 MEV SoOX 2 IND Go Be GARG TRM 

0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIES, 


92 URANIUM 232 NEUTRON CAPTURE CROSS SECTION 

231133 500o EV 10,0 MEV 2 USA Ro He CAHLBERG GA 


O: FOR FAST REACTOR BLANKETSo 


92_URANIUM 233 _ HALF LIFE 

231115 OoSX 1 USA NcSTEEN BET 

0: TO RESOLVE DISCREPANCIES, 


92URANIUM 233 _ NEUTRON TOTAL CROSS SECTION 

252021 2 So 3 MV 20o 0 MEV SoOX 2 INC Go Bo GARG TRM 




92 URANIUM 233 ELASTIC CROSS SECTION 

642205 1 Co OX JoGoTYROR WIN 

0: THERMAL AVERAGE INCIDENT ENERGYo 

0: FOR LONG TERM IMPROVEMENT OF THE ABSORPTION CROSS 

SECT ION c 

255022 20c 0 MEV SoOX D Go BoGARG TRM 

STATUS 

BET GREEN+ - NSE 54 18(1974), THERMAL VALUEo 

0: REQUIRED FOR THORIUM FUEL-CYCLE STUOIESo 


92 URANIUM 233 NEUTRON INELASTIC CROSS SECTION 

253022 20o 0 MEV 5c 0 X IND Gc Be GARG TRM 



92 URANIUM 233 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

621066 4 Co 0 KEV 7o 00 MEV 

A: NEED ENERGY DEPENDENCE TO 5 TO 10 PERCENT ABOVE 

0 e 5 MEVc 

92 URANIUM 233 NEUTRCN DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

&S223S 5o 00 MEV UK CoGoCAMPBELL WIN 



92 URANIUM 233 


6S235C 2=o3 MV lo 00 MEV 20o0X GER Ho GERWIN JUL 

O: ACCURACY INSUFFICIENT 

632552 1o 00 MEV lOoO MEV 20o0X GER He GERWIN 

o: ALPHA ALSO USEFULo 

O: ACCURACY INSUFFICIENTo 

63246 7 2So 3 MV lo 00 MEV NEC McEoAoHERMANS VDN 

Q: ALPHA ALSO USEFULC 

252033 10o0 KEV FR Ho TELL IER SAC 

O: EVALUATION PROBABLY NOT SUFFICIENT 

241112 lo00 MV 2o 00 EV USA NOSTEEN 

SHAPE IMPORTANT ESPECIALLY AT LOW ENERGYo 

ACCURACY REQUIRED - BELOW 0o5 EV. 1 PERCENTo 

ABOVE Oo 5 EV, 2 PERCENT, 

NEEDED TO CLEAR UP INTERPRETATION OF CAPTURE DATAo 

NEW REQUESTc 

1 Oo O KEV 1 o SO MEV WoDAVEY LAS 

O: ALPHA VALUES PREFERRED, 

O: NEEDED FOR ASSESSMENT OF 

POTENTIAL, 


U—2 33/THORIUM REACTOR 

253324 2=0 3 MV 20o0 MEV D Go Bo GARG TRM 



ORL WEST0N+ - NSE 42 143(1970), DATA THERMAL TO 1 EVo 

GEL CAO+ - JNE 24 111 (1970). DATA 18 EV TO lo 2 KEVo 

HAR ELWYN* - NP/A 146 337(1970), DATA TO 2o2 MEVo 

KAP REYNOLDS* - KAPL-M-7323, CAREFUL REICH-MOORE ANALYSI So 

92 URANIUM 233 NEUTRON TCTAL PHOTON PRODUCTION CROSS SECTION 

632332 120, KEV CoGoCAMPBELL W IN 

O: GAMMA SPECTRUM WANTEOo 

A." LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGY AND 

PHOTON SPECTRUMo 

o: FOR STUDY OF ACTIVATION AND HEAT RELEASE IN COREe 

92 URANIUM 233 NEUTRON 

621066 15,0 MEV lOoOX USA Po Bo HEMMIG AEC 

o: FOR CONTAMINATION OF U-233 BY U-2 32, 

FISSION LIST PAGE llo 64

92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED P 

652241 1 So 0 MEV lOoOX 1 FR Ao MICHAUDON BRC 

92 URANIUM 233 NEUTRON FISSION CROSS SECTION 

£21C3£ 1 C 00 MV 1C 00 KEV 1 USA 

NoSTEEN 

BET 

0: 

A: 

M : 

SHAPE IMPORTANT AT LOW ENERGlESo 

ACCURACY REQUIRED - OoS TO 1 PERCSNTo 

WANT ETA TO Oc 25 PERCENT BELOW 1 EVo 


621336 loOO MV loOO KEV lOoOX 1 USA 

Rohc CAHLBERG 

AOMOPERRY 

GA 

ORL 

Q: 

A: 

M: 

SHAPE IMPORTANT AT LOW ENERGIESc 

WANT ETA TO Cc 25 PERCENT BELOW 1 EVo 

WANT INTEGRAL ETA TO 1 PERCENT BELOW 1 KEVo 


£21032 1 c 00 KEV 3Go 0 KEV SoOX 3 USA 

CoEcTILL 

RoHoDAHLBERG 

PoB-.HEMMIG 

AoMoPERRY 

ANL 

GA 

AEC 

ORL 

A: 

WANT 2 PERCENT IN ETA AND INTEGRAL DATAo 

£Z10SS 1 Oo 0 KEV 15c 0 MEV loOX 1 USA 

Gc Ec HANSEN 

LAS 

92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION (CONTINUED) 

621043 1O 00 KEV 3O 00 MEV CoEoTILL 

PoBo HEMMIG 

ANL 

AEC 

0: CAPTURE CROSS SECTION EQUALLY USEFULo 

A: ACCURACY REQUIRED - 10 TO 20 PERCENT, 

WANT ETA TO 2 PERCENT FROM 1 TO 30 EVo 

632546 Io 00 KEV 1OOo KEV UK CoGoCAMPBELL WIN 


92 URANIUM 233 NEUTRONS EMITTED PER NEUTRON ABSORPTION (ETA) 

652545 Oo 20 EV OoSX JoGcTYROR WIN 

Q: VALUE RELATIVE TO 25=3 MV ETA WANTEDo 

A: ACCURACY IS FOR AVERAGE VALUES IN 0oC2 EV STEPSo 

0: FOR THERMAL REACTORSo 

Z41113 1 o 00 MV loOO EV 0 o 4 X 

o: THERMAL VALUE AND SHAPE NEEDEDo 

0: TO VERIFY FEW EXISTING RESULTS, 


Z41114 

A NoSTEEN BET 

Q: U-233 FISSION SPECTRUM AVERAGE VALUE NEEDEDo 

0: FOR ANALYSIS OF TARGET FAST MULTIPLICATION, 


STATUS- 

KAP REYNOLDS* - KAFL-M-7323. CAREFUL REICH-MOORE ANALYSISo 

92 URANIUM 233 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR) 

651225 

ICoO 

KEV 

lo SO 

MEV 

USA NoSTEEN BET 


0: TO LOOK FOR STRUCTURE BELOW 1 MEVo 


651230 

30o0 

KEV 

3o 00 

MEV 

Ro H, DAHLBERG 

AoMoPERRY 

GA 

ORL 


0: TO LOOK FOR STRUCTURE BELOW 1 MEVo 


651443 

30e 0 

KEV 

NoSTEEN 

RoHoDAHLBERG 

AoMcPERRY 

BET 

GA 

ORL 

REQUIRE Oo 25 PERCENT ACCURACY TO 30 EV, 1 PERCENT 

FROM 30 EV TO 1 KEV, AND 2 PERCENT ABOVEo 

INTERMEDIATE ACCURACY OF lo5 PERCENT LSEFULo 


632466 30,0 KEV 1 Oo 0 MEV HoGERWIN 

Z41206 SOoO KEV So 00 MEV OoSX WoDAVEY LAS 

0: NEEDED TO CHECK POSSIBLE STRUCTURE (DIP) IN FEW 

100-KEV REGIONO 

NEEDED FOR ASSESSMENT OF U-233/TH0RIUM REACTOR 

POTENTIAL, 


IAE MANERO+ - REA 10 637(1972), REVIEW, 

RPI REED* - USNDC-7 202( 1973), IN PROGRESS THERMAL TO 100 EVo 

FOA CONDE - MORE WCRK REQUIRED CN CF-252 NU STANDARD AND ENERGY DEPENDENCE TO GET 0o25 PERCENT 

ACCURACYo 

MORE WORK REQUIRED IN 30 EV TO 1 KEV RANGE TO REACH 1 PERCENT ACCURACY, 

BELOW 4 MEV MORE WORK REQUIRED FOR BETTER THAN 2 PERCENT ACCURACYo 

NO DATA AVAILABLE BETWEEN 4o5 AND 14 MEVo 

92 URANIUM 233 NE UTRGN DELAYED NEUTRONS EMITTED PER FISSION 

Z41116 

O: TO RESOLVE DISCREPANCIESo 


STATUS 

A I TUTTLEo - NSE 56 37(1975). REVIEW WITH RECOMMENCED VALUES, 

92 URANIUM 233 NEUTRON FISSION PRODUCT MASS YIELD SPECTRUM 

621355 2 5o 3 MV 3,OX USA No STEEN BET 

Q: CUMULATIVE AND DIRECT YIELD OF XE-135 INCLUDING 

15 MINUTE ISOMER REQUIREDo 

o: FOR CALCULATION OF FISSION PRODUCT POISONSo 

6Z13S6 

loOX 

Q: YIELD OF CS-137 WANTEOo 

o: FOR BURN UP INDICATOR STANDARDo 

FISSION LIST PAGE 1 lo 83

92 URANIUM 235 NEUTRON DELAYED NEUTRONS E M I T T E D P E R FISSION (CONTINUED) 

621597 2Ec3 MV SoOX 2 USA NoSTEEN BET 

0: YIELD OF ND-147 AND SM-149 WANTEDo 


711.661 2 So 3 MV loOX 2 CAN Wo He WAL KER CRC 

o: YIELD OF XE-135 WANTEDo 

O: FOR CALCULATION OF FISSION PRODUCT ABSORPTIONo 

STATUS 

STATUS 

ANL GLENDENIN* - WORK IN PROGRESS, 

I IT REEDo - DATA A VAILABLEo 

92 URANILM_233 NEUTRON RESONANCE PARAMETERS 

£21195 2 5o 3 MV 5o 00 KEV 2 USA CoEoTILL ANL 

Po Be HEMMIG 

AEC 

0: MULTILEVEL PARAMETERS AND STATISTICAL 

DISTRIBUTIONS WANTED IN EV RANGEo 

A: ACCURACY 10 PERCENT WANTED TO 100 EV. 30 PERCENT 

ABOVEo 

0: FOR THERMAL BREEDER CALCULATIONSo 

212654 2 OOo EV- 10o0 KEV SoOX 3 FR Jo Ye BARRE CAD 


STATUS 

STATUS 

COL RAHN+ - USNCC-1 70(1972), PARAMETERS FOR 38 RESONANCESo 

SAC BLGNS+ - EANDC(E)-150 * ANALYSIS IN PROGRESSo 

LAS KEYW0RTH+ - NCSAC-42 153(1971). EXPERIMENT IN PROGRESS: 

92URANIUM 234 NEUTRON TOTAL CROSS SECTION 

255 026 2So3 MV 2 0o 0 MEV SoOX 2 INC Go Bo GARG TRM 



92URANIUM 234 NEUTRCN _ ELASTJCCROSS SECTION 

255522 2 So 3 MV 2 Oo 0 MEV SoOX 2 INC Go Be GARG TRM 




255525 20o 0 MEV SoOX 2 INC Go Bo GARG TRM 

O: REQUIRED FOR THORIUM FUEL-CYCLE STUD IE So 



691465 1o00 MV 1Oo 0 MEV 2 USA CoEcTILL ANL 

A: ACCURACY 3 PERCENT BELOW 2 EV, 6 PERCENT BELOW 10 

KEV. 10 PERCENT ABOVE 10 KEVo 

,692356 1o 00 EV 10o0 MEV ISoOX 2 GER HoGERWIN JUL 

232694 1Oo 0 KEV SoOX 3 FR HoTELLIER SAC 

252B2S 2So3 MV 20o0 MEV SoOX 2 IND Go Bo GARG TRM 



STATUS 

STATUS 

ORL KASTEN - REA 8 473(1970). REVlEWo 

RPI BLOCK* - MEASUREMENTS FLANNEOo 

92 URANIUM 234 NEUTRCN N.2N 

662356 1 So 0 MEV lOoOX 1 FR AoMICHAUDON BRC 

92 URANIUM 234 NEUTRCN N.3N 

662051 1 So 0 MEV 1SoOX 1 FR AoMICHAUDON BRC 

92 URANIUM 234 _NEUTR0N FlisiCN CROSS SECTION 

6S2352 4c00 MEV 1Oo 0 MEV 15oOX 2 GER HoGERWIN JUL 

0: SPECTRUM INDEXo 



223030 2Eo 3 MV 20o0 MEV SoOX 2 INO Go Ec GARG TRM 



STATUS 

STATUS 

HAR JAMES* - AERE-FR/NP15 (1972), DATA 180 KEV TO 6o MEVc 

92 URANIUM235 DISCRETE LEVEL STRUCTURE (ENERGY, SPIN, PARITY) 

£52525 2 GER FoWELLER KFK 

o: ENERGY, SPIN ANC PARITY WANTED FOR LEVELS BELOW 

1 c 0 MEVc 

STATUS T STATUS 

LAS RICKEY* - FR/C S 2072( 1972 >o 

92 URANILM 225 NEL'TRCN ELASTIC CROSS SECTION 

£S22£$ JoGoTYROR WIN 

o: THERMAL AVERAGE INCIDENT ENERGYo 

O: FOR LONG TERM IMPROVEMENT OF THE ABSORPTION CROSS 

SECT ION, 

2320£.7 loOO KEV 15o0 MEV lOoOX FR AcMICHAUDON BRC 

0: FOR CRITICAL ASSEMBLIESo 

92 URANIUM 235 DIFFERENTIAL ELASTIC CROSS SECTION 

631232 loOO MEV SoOO MEV COECTILL 

P o Be HEMMIG 

ANL 

AEC 

ENERGY RESOLUTION AT LEAST Oo 5 MEVo 

NEEDED FOR ANALYZING FAST CRITICAL EXPERIMENTSo 

.732065 lo 00 KEV 1 5o 0 MEV lOoOX 1 FR Ao M I CHAUDON BRC 


STATUS 

STATUS 

GEL KNITTER* - ZP 257 108( 1972), DATA 1o 6 TO 5o5 MEVo 

ANL GUENTHER* - USNOC-11 25(1974), EXPERIMENTAL AND THEORETICAL WORK IN PROGRESS TO 4 MEVo 

92 URANILM 235 NEUTRON INELASTIC CROSS SECTION 

632363 1 So 0 MEV lOoOX SWC Ho HAEGG8LOM AE 

0: FAST CRITICAL SYSTEMSc 

232070 15o 0 MEV lOoOX FR AoMlCHAUDON BRC 


253023 800o KEV So 00 MEV L oN,USACHEV FEI 

A: FROM 0 c 8 - lc 4 MEV ACCURACY 15 PERCENT, 


FROM lo 4 - 2o 5 MEV ACCURACY 17 PERCENT, 


FROM 2o 5 - 5,0 MEV ACCURACY 30 PERCENT. 


O: NEED FOR FAST REACTOR CALCULATION 

FOR MORE DETAIL SEE INTRODUCTIONc 


92 URANIUM 235 NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

£52363 

ISoO MEV 20o OX 

FoWELLER 

KFK 

ACCURACY OF 10 PERCENT REQUIRED BELOW lo 5 MEVo 

RESOLUTION FOR INCIDENT AND EXIT NEUTRON ENERGIES 

100 KEVo 

FAST REACTOR CALCULATIONSo 

213006 

1 5o 0 MEV 

CCP 

MoNoNIKOLAEV 

FEI 

CROSS SECTION FOR INELASTIC REMOVAL BELOW FISSION 

THRESHOLDS OF U-238 (7 PERCENT ACCURACY) AND OF 

PU—240 OR NP-237 (10 PERCENT ACCURACY) WANTEDo 

EXCITATION CROSS SECTION FOR LOW LYING LEVELS 

REQUESTED WITH 15 PERCENT ACCURACYo 

TEMPERATURES OF THE INELASTIC SCATTERING SPECTRA 

AS WELL AS DIRECT AND PRE-EQU1LI BR IUM MECHANISM 

CONTRIBUTIONS IN THE CONTINUUM ARE OF INTERESTo 

SEE GENERAL COMMENTS IN THE INTRODUCTION 

22102£ 50o 0 KEV 6o 00 MEV lOoOX CoEoTILL 

Po Bo HEMMIG 

ANL 

AEC 

LOW ENERGY NEUTRONS MUST BE INCLUDEDo 

ABSOLUTE SPECTRA AT 30 AND 75 DEGREES MAY SUFFICEo 

INCIDENT AND EXIT ENERGY RESOLUTIONS lOo PERCENTo 


92 URANIUM 235 NEUTRON ENERGY CIFFcRENTIAL INELASTIC CROSS SECTION (CONTINUEDI 

STATUS 

STATUS 

GEL KNITTER* - ZP 257 108(1972). DATA 1=5 TO 2o3 MEVc 

LRL KAMMERDIENER - UCRL-51232 (1972), DATA AT 14 MEVo 

ALD SATCHELOR+ - A taRE/0-55/69, DATA 2 TO 4 MEV; 

ANL GUENTHER+ - USNCC-11 25(1974), EXPERIMENTAL AND THEORETICAL WORK IN PROGRESS TO 4 MEVc 

92 URANIUM 235 ' NEUTRON DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

652052 1 3o 0 KEV lOoC MEV lOoOX 1 JAP He MATSUNOBU SAE 

O: CROSS SECTIONS FOR EXCITATION OF INDIVIDUAL LEVELS 

ALSO WANTEDo 

A: ENERGY RESOLUTION 1 TO 2 PERCENT DESIREDo 


FOR EVALUATION OF NUCLEAR DATAo 

NO EXPERIMENTAL DATA ABOVE 7o5 MEVc 


653052 3 OOo KEV 1 Oo 0 MEV lOoOX 1 BAN MoMc ISLAM RAM 


.742071 1 5o 0 MEV 20 o 0 X 2 FR AoMICHAUDON BRC 


92URANILM235 _ NEUTRCN TOTAL SCATTERING_CROSS SECTJON_ 

752026 1o 00 KEV 1Oo 0 MEV 2o OX 1 JAP He MATSUNOBU SAE 

A: ENERGY RESOLUTION - 1 TO 2 PERCENTo 

o: EVALUATION OF U-235 NUCLEAR DATA AND FOR REACTOR 

DESIGN CALCULATIONSo 

THE EXPERIMENTAL DATA ARE VERY POORo 

NO EXPERIMENTAL DATA FROM 5o5 MEV TO 10 MEVo 


92 URANIUM 235 NEUTRCN DIFFERENTIAL TOTAL SCATTERING CROSS SECTION 

252027 1o 00 KEV 1Oo 0 MEV 1 JAP He MATSUNOBU SAE 


ENERGY RESOLUTION - 1 TO 2 PERCENTo 

o: EVALUATION OF U-235 NUCLEAR DATA AND FOR REACTOR 



NO EXPERIMENTAL DATA FROM 5o 5 MEV TO 10 MEVo 

Ml NEW REQUEST.; 

92 URANIUM 235 NEUTRON NCN-ELASTIC CROSS SECTION 

652561 1 So 0 MEV 5 FoWELLER KFK 

A: ACCURACY 10 PERCENT REQUIRED TO lo 5 MEV AND 20 

PERCENT ABOVEc 

ENERGY RESOLUTION ABOUT 100 KEVo 

655051 1 00c KEV lOoO MEV lOoOX BAN MoMoISLAM RAM 



662055 1o 00 KEV 1 Oo 0 MEV JAP Sc KATSURA GI 

HoMATSUNOBU 

JAE 

SAE 

0: ALPHA ALSO WANTEOo 

A: REQUIRED ACCURACY - 

RESOLUT ION - 1 TO 2 


NUCLEAR DATA EVALUATIONc 

5 TO 10 PEPCENTo 

PERCENTo 

NO EXPERIMENTAL DATA ABOVE 2 


652576 1 Oo 0 KEV lOoO MEV 

A: ACCURACY TO OBTAIN 1 PERCENT IN ALPHAo 

o: ANALYSIS OF CRITICAL EXPERIMENTSo 

653060 3Oo 0 KEV BAN MoMoISLAM RAM 


241112 1o 00 MV lo 00 EV A NoSTEEN BET 

Q: SHAPE ESPECIALLY IMPORTANT AT LOW ENERGYo 


242005 200o EV SOOo KEV SWD HoHAEGGBLOM AE 


242028 3o 00 MEV FR AoMICHAUDON BRC 



92 URANIUM 235 NEUTRON CAPTURE CROSS SECTION (CONTINUED! 

253002 So 00 KEV 1Oo 0 MEV 1 CCF LoNoUSACHEV FEI 

A: FROM Oo 5 - 100 KEV ACCURACY 40 5 PERCENT, 

PRIORITY 2 ACCURACY 3o 7 PERCENTo 

FROM Oo 1 - 0 o 8 MEV ACCURACY 10 PERCENT, 


FROM OoS - Ao 5 MEV ACCURACY 50 PERCENT, 


ABOVE 4o 5 MEV REQUIREMENTS 2 TIMES WEAKER, 

0: NEED FOR FAST REACTOR CALCULATIONSo 

FOR MORE DETAIL SEE INTRODUCTIONo 


STATUS 

STATUS 

ORL PEREZ* - ISNOC-l 145(1572), DATA So EV TO 10 KEVo 

ORL OE SAUSSURE+ - PR/C 7 2018(1973). ANALYSIS TO 60 EVo 

92 URANIUM 235 NEUTRON CAFTUfii GAMMA RAY SPECTRUM 

621105 2 5o 3 MV 15o 0 EV lOoOX 2 USA NoSTEEN BET 

621103 2 5o 3 MV 20o0X 2 USA RoEHRLICH KAP 

STA TUS 

STATUS 

ATI FLECK* - AKE 21 136(1973 )» 

GEL CORVIt - NP/A 2C3 145(1973). DATA FCR 14 RESONANCESo 

NYU GRAVES - DA/B 32 4793(1972). EPITHERMAL NEUTRONSo 

9 2 URANIUM 235 _ NEUTRON FHCTON PRODUCTION CROSS SECTION IN INELASTIC SCATo 

655052 3GOo KEV 4o 00 MEV lOoOX 1 BAN MoMoISLAM RAM 

O: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REOUI REOo 


92 URANIUM 235 NEUTRON TCTAL PHOTON PRODUCT ION CROSS SECTION 

652562 120o KEV 20o0X Cc Gc CAMPBELL 

AoWHITTAKER 

WIN 

UK W 

o: GAMMA SPECTRUM WANTEDo 

A: LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGY AND 

PHOTON SPECTRUMc 

O: FOR STUDY OF ACTIVATION AND HEAT RELEASE IN CORE 

232565 1o 00 KEV 1 5o 3 MEV 1 OoOX FR Ao MICHAUDON 

0: FOR SHIELDING, 

92 URANIUM 235 NEUTRON N.2N 

252026 SoOO MEV 1Oo 0 MEV HoMATSUN08U SAE 


O: EVALUATION OF U-235 NUCLEAR DATA AND FOR REACTOR 




92 URANILM 235 NEUTRCN 

232022 15o 0 MEV FR Ao MICHAUDON 6RC 



661032 1 Co 0 KEV 

15oC MEV loOX 1 USA GoEcHANSEN LAS 

651231 loOO EV 

lo 00 KEV 3 o OX 2 USA BoHUTCHINS GEB 

o: USED AS STANDARD AT HIGHER ENERGlESo 

651235 1 Oo 0 KEV 1 Ao 0 MEV 1 oOX USA RoSoCASWELL NBS 


691236 loOO KEV 14o 0 MEV CoEoTILL ANL 

Po Be HEMMIG 

AEC 

FoCcMAIENSC HE 1N ORL 

REQUIRED IS RATIO OF U-235(N,F) TO B-10(N.ALPHA), 

AND TO H-l(N.P) TO 1 PERCENTo 

INTERMEDIATE ACCURACY OF 3 PERCENT USEFULo 

NEEDED TO COMPARE STANDARDSo 

651435 loOO KEV 14o 0 MEV USA BoHUTCHINS 

Po BoHEMM I G 

GEB 

AEC 

O: ABSOLUTE VALUES REOUIREDo 

A: FROM 1-20 KEV. ACCURACY 2 PERCENT, 5 PERCENT 

USEFULo 

FROM 20 KEV - 3 MEV, ACCURACY 1 PERCENT. 3 PERCENT 

USEFULo 

FROM 3-14 MEV, ACCURACY 2 PERCENT, 

5 PERCENT USEFULo 

0: FOR FAST REACTOR CALCULATIONS AND FOR USE AS A 

STANDARD, 


92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PERFISSION (CONTINUED) 

695366 10 Co EV 

1Oo 0 

MEV 

1-oC-ERW IN 

JUL 

A: ACCURACY 5 PERCENT FOR 100 EV - 10 KEV, 

2 PERCENT FOR 10 KEV - 1 MEV 

AND 5 PERCENT FOR 1-10 MEVo 

O: SPECTRUM INDEXo 

STANDARD CROSS SECTIONc 

692366 1o 00 MEV 

So 00 MEV 3o0X 

CoGcCAMPBELL * IN 

A: ACCURACY FOR AVERAGE VALUE OF THE ERROR BETWEEN 

E AND 2Eo 

0: STANDARD FOR PU CROSS-SECTIONSo 


692496 2 00c EV SOOo KEV 2oOX Ho HAEGGBLOM AE 


693054 2 5c 3 MV 1 So 0 MEV MoMoISLAM RAM 


214007 So 00 KEV 7o 00 MEV 2o0X MoNjNIKOLAEV FEI 

BELOW 20 KEV MEASUREMENTS OF TRANSMISSION CURVES 

BY FLAT RESPONSE DETECTOR AND BY SELF DETECTION 

METHOD WITH FISSION DETECTOR WANTED FOR 

SELFSHIELDING EVALUATIONo 

THESE CURVES MUST BE MEA SUREO WITH ATTENUATIONS OF 

THE PRIMARY BEAM DOWN TO lo PERCENTo 

AVERAGE CS IN FISSION NEUTRON SPECTRUM OF CF-252 

TIMES NU-BAR OF CF-252 IS OF- GREAT INTEREST FOR 

REDUCING THE DEPENDENCE OF THE ACCURACY OF NEU- 

TRON PRODUCTION CALCULATIONS UPON THE ACCURACY 

OF THE CF-252 NU-BAR STANDARD (REQUIRED ACCURACY 

1 PERCENT >c 

ACCURACY DETERMINED BY USE OF THIS CROSS SECTION 

AS STANDARD IN FISSION AND CAPTURE MEASUREMENTS 

=OR OTHER ISOTOPESc 

IF MEASUREMENT IS ABSOLUTE AND PU-239 AND U-238 

FISSION CROSS SECTIONS ARE MEASURED RELATIVE TO 

U-235 FISSION. THEN 2c 0 PERCENT ACCURACY IS 

REQUIREDo 

BEST ACCURACY OF lc 5 PERCENT DESIRABLE IN 1o2 TO 

2,5 MEV REGION BECAUSE OF U-238 FISSION CROSS 

SECTION NORMALIZATION 


REQUEST CONSIDERED FULFILLED, WHEN AT LEAST THREE 

MEASUREMENTS WITH DIFFERENT METHODS AGREE WITHIN 

REQUESTED ACCURACYo 


241118 1o 00 MV lo 00 EV NoSTEEN BET 

SHAPE ESPECIALLY IMPORTANT AT LOW ENERGYc 

NEW REQUEST, 

24120 9 4 OOo KEV 2o 00 MEV Wo DAVEY LAS 

Q: A RELATIVE MEASUREMENT NORMALIZED TO EXISTING 

DATA ABOVE 1 MEV IS SUFFICIENT 

0: EXTENSION OF LASL ABSOLUTE MEASUREMENT BELOW 1 MEV 

TO OVERLAP IMPORTANT LOWER ENERGY DATAo 

A REFERENCE WHICH IS VITAL TO ALL REACTOR STUDIESo 


24202- 1 So 0 MEV AoMICHAUDON 

A: ACCURACY 3 PERCENT TO 1 KEV, 

o: FOR' CRITICAL ASSEMBLIESc 

2 PERCENT ABOVEo 

242113 

2o 0 X 

NEUTRON DOSIMETRY GROUP GEL 

0: AVERAGE CROSS SECTION IN A U-235 FISSION SPECTRUM 

DESIREDo 

O: FOR NORMALIZATION OF AVERAGE CROSS SECTIONS FOR 

DOSIMETRY PURPOSES, 

252023 lo 00 KEV lOOo KEV 

2o OX 

HoMATSUNOBU 

SAE 

o: ABSOLUTE MEASUREMENT WANTEDo 


o: EVALUATION OF u-235 NUCLEAR DATA AND FOR REACTOR 

DESIGN CALCULATIONSc 

DISCREPANCIES BETWEEN THE EXPERIMENTAL DATA ARE 

VERY REMARKABLE IN THE ENERGY RANGE BELOW 

70 KEVo 


252024 1 COo KEV 

loOO 

MEV 

JAP 

HoMATSUNOBU 

SAE 

Q: ABSOLUTE MEASUREMENT WANTEDO 


o: EVALUATION OF u-235 NUCLEAR DATA AND FOR REACTOR 



252025 loOO MEV 

20o 0 

MEV 

HoMATSUNOBU 

SAE 

O: ABSOLUTE MEASUREMENT WANTEOo 


ENERGY RESOLUTION - 1 TO 2 PERCENTo 

O: EVALUATION OF U-235 NUCLEAR DATA AND FOR REACTOR 


THE EXPERIMENTAL DATA ARE COMPARATIVELY POOR IN 

THE ENERGY RANGE ABOVE 6 MEV EXCEPT 14 MEV DATAo 




Z54ooe So OC KEV 10=0 MEV LoNoUSACHEV FE I 

A: FROM 0=5 

PRIOR ITY 

FROM Ool 

PRIORITY 

FROM 0 o 8 

PRIORITY 

ABOVE 4o 5 

0: NEED FOR 

STANDARD 

- 100 KEV ACCURACY 2c8 PERCENT, 

2 ACCURACY 1 c 2 PERCENTc 

- 0 o 8 MEV ACCURACY 2o1 PERCENT, 

2 ACCURACY lol PERCENTo 

- 4 o 5 MEV ACCURACY 2o9 PERCENT, 

2 ACCURACY lo4 PERCENTo 

MEV REQUIREMENTS 2 TIMES WEAKERo 


CS ABOVE 100 KEVo 


M: NEK REOUE STc 

STATUS- 

-STATUS 

HAR SOWERBY* - ANE 1 409(1974), EVALUATION OF CATA PUBLISHED BEFORE ABOUT JANUARY 1972o 

ooESTIMATEC UNCERTAINTY IN FISSICN CROSS SECTIONOO 

oo IOC EV TO 4 KEV oooo 3o 3 PERCENT 0c 

oo 4 KEV TO 20 KEV oooo BETTER THAN 4 FERCENTo 

oo 20 KEV TO 100 KEV oooo 4 TO 5 PERCENT oo 

oo 100 KEV TO 3 MEV oooo 3 TO 4 PERCENT oo 

oo 3 MEV TO 20 MEV oooo 4 TO 7 PERCENT EXCEPT' 

oo NEAR 14 MEV ooooooooooo 2 PERCENT oc 

FOLLOWING CATA AVAILABLE SINCE SOWERBY EVALUATION 

LRL 

LRL 

ANL 

ORL 

M HG 

LAS 

ORL 

SAC 

KFK 

HAR 

GEL 

ORL 

GEL 

KFK 

NBS 

NBS 

HAR 

CZIRR* 7EWASH. DATA 1 KEV TO 20 MEV. MEASUREMENTS TO THERMAL ENERGIES IN PROGRESSo 

CZIRR+ - NSE 5 7 18(1975). DATA 3 TO 20 MEVc REPORTED ACCURACY 1 PERCENT FROM 3 TO 7 MEV, 

2 PERCENT AT 14 MEV AND 6 PERCENT AT 20 MEVo 

POENITZ - NSE 53 370(1974), DATA 35 KEV TO 3o5 MEV 

PEREZ* - NSE EE 203(1974), DATA 2 TO 100 KEVc 

GILLIAM* - USNDC-11 162( 1974), IN PROGRESS AT 960 KEV, ALSO SEE THESIS( 1973 )o 

HANSEN* - USNDC-11 147(1974), TELESCOPE EFFICIENCY BEING STUDIEDc PRELIMINARY DATA WERE CONSIDERED 

IN EVALUATION BY SCWERBYo 

PEREZ* - l#SE 52 46(1973). DATA 8 EV TO 10 KEVo 

BLCNS - NSE 51 130(1973). DATA 18 EV TO 30 KEVo 

KAPPELFRo - KFK-1772( 1973 I , DATA 0c5 TO lc2 MEVc 

GAYTHER* - 72VIENNA 201. CATA 1 KEV TO 1 MEVo 

KNITTER* - ZP 2 = 7 108( 1972), DATA lc5 TO 2o3 MEVo 

GWIN* - USNDC-3 149(1972), IN PROGRESS THERMAL TO 200 KEVo DATA AVAILABLE FROM DATA CENTERSo 

THEOBALD* - NEANCC(E)-161 202(1974), IN FFCGRESS 1 TO 500 KEVc 

BROTZ* -NEANDC

92 URANIUM 235 NEUTRONS EMITTED PER NEUTRON ABSORPTION (ETA I 

62110.0 25o 3 MV 5Co 0 KEV Cc Eo TILL 

Be HUTCHINS 

Po Be HEMMIG 

ANL 

GEB 

AEC 

ACCURACY 1/2 PERCENT AT THERMAL. 

ELSEWHERE c 

2 PERCENT 

652320 JcGcTYROR WIN 

0: VALUE RELATIVE TO 25o 3 MV ETA WANTEOo 

A: ACCURACY IS FOR AVERAGE VALUES IN 20 MV STEPS 

UP TO Gc 2 EV. AND IN 50 MV STEPS ABOVEo 

o: FOR TEMPERATURE COEFFICIENT WORKc 

241115 lo OS EV C o4X 

BET 

o: SHAPE ESPECIALLY 


IMPORTANT AT LOW ENERGYo 

.741121 

STATUS 

SoOX 

o: 

O: 

M: 

U-235 FISSION SPECTRUM AVERAGE VALUE WANTEDo 

FOR ANALYSIS OF TARGET FAST MULT I PL ICATIONo 

NEW REQUEST: 

HAR 

MOXON+ (1974), FEASIBILITY ASSESSMENT IN FROGRESSo 


651252 2Ec3 MV 3o 00 MEV 1 o 0 X USA Co Eo TILL 

BoHUTCHINS 

PcB:HEMMIG 

ANL 

GEB 

AEC 

ACCURACY OF 2 PERCENT USEFULo 

NEEDED AS A CROSS CHECK WITH OTHER ISOTOPESo 

21400S 25c 3 MV 2o 50 MEV M0N3NIKOLAEV FE I 

RATIO TO CF-252 NU REQUIREDo 

ABSOLUTE MEASUREMENTS OF U-235 NU-BAR FOR THERMAL 

N5UTRONS WITH ACCURACY NOT WORSE THAN Oo5 PER- 

CENT AS WELL AS ETA MEASUREMENTS tOULO BE USEFUL 

FOR LOWERING THE DEPENDENCE ON THE CF-252 

STANDARDo 

ENERGY DEPENDENCE OF NU IS WANTED WITH 0c 7 

LETHARGY RESOLUTION IN THE REGION BELOW 2o 5 MEVo 

SEE GENERAL COMMENTS IN THE INTROOUCTIONo 


742025 1 5o 0 MEV AoMICHAUDON 

A: ACCURACY 2 PERCENT TO 1 KEV. 

O: FOR CRITICAL ASSEMBLIES: 


25401C 5o00 KEV I Oo 0 MEV LoNiUSACHEV FE I 

STATUS- 

o: 

M: 

FROM 0c 5 - 100 KEV ACCURACY lc 2 PERCENT. 

PRIORITY 2 ACCURACY Oo 5 PERCENTc 

FROM Co 1 - Co 8 MEV ACCURACY lc 0 PERCENT. 

PRIORITY 2 ACCURACY Oo 5 PERCENTc 

FROM OoB - 4o 5 MEV ACCURACY 2c1 PERCENT, 


ABOVE A o 5 MEV REQUIREMENTS 2 TIMES WEAKERo 



NEW REQUESTo 

I AE 

MANERO+ 

REVlEWo 

KFK BANDL+ - 

LRL HO WE + - 

RPI REED + - 

(1574 ) . DATA 1 TO 200 EVc 

USNDC-7 202(1973). IN PROGRESS TO 40 EVc 

BRC 

FREHAUT+ 

FOA CONDE - : 

92 URANIUM 235 DELAYED NEUTRONS EMITTED PER FISSION 

651266 25o3 MV 5o 00 MEV Po Be H.EMM I G AEC 

Q: DELAYED NEUTRON ENERGY SPECTRUM WANTEOo 

YIELD.HALF-LIFE. AND ENERGY NEEDEDo 

O: NEEDED FOR ANALYSIS OF FAST CRITICALS AND TO CHECK 

EXISTING DATAo 

241120 3 o OX 

FOR THE ENTIRE ENERGY RANGEo 

TO RESOLVE UNCERTAINTIES IN AVAILABLE DATAo 

NEW REQUESTc 



STATUS . STATUS 

AI TUTTLEo - NSE 56 37(1975), REVIEW WITH RECOMMENCED VALUESo 

ANL COXo - ANL/NCM-5 ( 1974),REV IEWo 

HFA SHALEV+ - NSE 51 52(1973), SPECTRUM AVERAOEo 

IAE MANERO* - REA 1C 637(1972), REVIEWo 

KFK FI EG - EANCC(E)-157 (19731. WORK IN PROGRESS; 

FEI TARASKO* - YF 17 1149(1973). IN FROGFESSc 

SOR AMI EL - 73E0LCGNA.REPo13o TC 15 MEVo 

LAS KRICK* - NSE 47 311(1972)o Go! TC 6o5 MEVo 

92 URANIUM 235 NEUTRON ENERGY SPECTRUM OF FISsloN NEUTRONS 

651256 

3c 00 MEV CoEcTILL 

Po Bo HEMMIG 

ANL 

AEC 

o: VERIFICATION OF FISSION SPECTRUM NEEDEDo 

651252 

2 5o 3 MV 

RcEHRLICH 

KAP 

A: OUTGOING NEUTRON ENERGY RESOLUTION 5 PERCENT FOR 

NEUTRON ENERGIES BELOW 0o3 MEVo 

O: VERIFICATION OF FISSION SPECTRUMo 


£52.22.6 

1 OOo KEV 

2o 0% 

CoGoCAMPBELL 

AoWHITTAK ER 

ScB:WRIGHT 

WIN 

UK W 

HAR 

ACCURACY FOR AVERAGE E'c 

ACCURACY 10 PERCENT ON NUMBER OF NEUTRONS 

ABOVE 5 MEV AND BELOW o25 MEVo 

LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGYc 


FOR REACTION RATE ANALYSISo 

221060 1 oOX NcSTEEN BET 

O: VERIFICATION OF FISSION SPECTRUM NEEDEDc 

242.022 1 So 0 MEV SoOX 1 FR Ac MI CHAUDON BRC 


STATUS 

ST 

GEL KNITTER* - ZP 257 108(1972), OATA loS TO 2oJ MEVo 

LAS AUCHAMPAUGH+ - USNDC-3 118(1972). DATA AT lo8 MEVo 

KFK WERLE+ - JNE 26 165(1572), DATA 100 KEV TO 9o5 MEVc 

AE ALMEN+ - AE-425 (1971), DATA AT 950 KEVc 

ANL SMITH - ANL-7 510 18(1972), WORK I" PROGRESSc 

CAD ABRAMS0N+ - NEANDC(E)-161 34(1974), WORK IN PROGRESS AT 30 KEVc 

AE JOHANSSON* - EANOC(OR)-135 47(1973), PRELIMINARY RESULT AT 530 KEVc WORK IN PROGRESS AT 2o1 MEVo 

GEL KNITTER* - NSE 50 108(1973). OATA AT 0o4 MEVo 

HAR ADAMSo - (1574), PRELIMINARY OATA AVAILABLE FROM JOINT HAR/AE STUDYo 


£21105 2oOX A NoSTEEN BET 

O: CUMULATIVE AND DIRECT YIELDS OF XE-135o 

O: CALCULATION OF FISSION PRODUCT POISONSo 


621106 2 So 3 M V 

Q: YIELD OF CS- 137 WANTED, 

o: FOR BURN UP INDICATOR STANOAROo 

621102 2 So 3 MV 

Q: 

o: 

YIELD OF SM-149 AND ND-147 WANTEDo 

CALCULATION OF FISSION PRODUCT POISONSo 

211602 loOX N Wo Ho WALKER CRC 

O: YIELD OF XE-135 WANTED, 

0: CALCULATION OF FISSION PRODUCT POISONSo 


92 URANIUM 235 NEUTRON DELAYED NEUTRONS E M I T T E D P E R FISSION (CONTINUED) 

STATUS 

STATUS 

KUR MILLER* - SJA 27 231(lS68)o 

SRE HILLER - KT 12 465(197C) 

CCP GRECHUSHKINA - TABLES SHOWING THE COMPOSITION OF PROMPT FISSION PRODUCTS FROM U-235. U-238, AND 

PU-239 FISSICN. ATGMIZCAT, MOSCCW11964)c 

AE FORSYTH* - 70 KARLSRUHE VCLol Po521o 

CCP GliSEV - PROTECTION AGAINST GAMMA RADIATION FROM FISSION PRODUCTS. ATOM I ZDA T, MOSC 0W( 1 968) o 

SGA LAMMER* - 73 PARIS PAPER 13, EVALUATIONo 

HAR CROUCH - 73 PARIS PAPER 94, EVALUATICNo 

GRE DEVILLERS* - 73 PARIS PAPER 63. EVALUATIONo 

CRC WALKER - 73 PARIS PAPER 34. EVALUATICNo 

GEV MEEK + - NECO-12154. EVALUATIONo 

ANL GLENDENIN* - WCRK IN PROGRESSo 

92 URANIUM 235 NEUTRCN RESONANCE PARAMETERS 

65-1262 25o3 MV 2 OOo EV lOoOX 1 USA CoEoTILL ANL 

NoSTEEN 

BET 

BohUTCHINS 

GEB 

P o Bo HEMMIG 

AEC 

Q: NEEDED TO AS HIGH AN ENERGY AS POSSIBLEo 

MULTILEVEL FIT WANTED WHERE FEASIBLEo 

A: NEED 10 PERCENT ACCURACY BELOW 100 EVo 

O: NEEDED FOR EXTRAPOLATION TO UNRESOLVED RESONANCE 

REGIONo 

652355 150o EV 200o EV lOoOX 2 GER FoWELLER KFK 

762525 1o 00 EV 200o EV 3oOX 2 FR HoTELLIER SAC 

0: FOR RESONANCE SELF SHIELD INGc 

STATUS 

STATUS 

COL o (1974), NEW RESULTS USING FRAGMENT DETECTIONo 

BNL REDDINGIUS* NF/A 218 84(1974), POLARIZED BEAM AND TARGET, DATA FOR RESONANCES BELOW 14 EVo 

LAS KEYWORTH* - PRL 31 1077(1973), POLARIZED EEAM AND POLARIZED TARGET. DATA FOR 65 RESONANCES BELOW 

92 URANIUM 235 NEUTRON D E L A Y E D N E U T R O N S E M I T T E D P E R F I S S I (CONTINUED) 

O N 


o£2LS£ 1 5o 0 MEV Ac MICHAUDON BRC 

0: EVALUATION MAY BE SUF=ICIENTo 

652380 4o OC MEV 10C 0 MEV HcGERWIN 

212062 5 00c EV 15o 0 MEV J c Yc EARRE CAD 

0: WANTED RELATIVE TO U-235 FISSION CROSS SECTIONo 


215013 100c 5o 00 MEV 

MoNcNIKOL AEV 

FEI 

0: 

M: 

RATIO WANTED RELATIVE TO U-235o 

AVERAGE CS IN FISSION NEUTRON SPECTRUM OF CF-252 

TIMES NU-BAR OF CF-252 WOULD BE VERY USEFUL 

(REQUIRED ACCURACY 1 PERCENT >c 

SEE GENERAL COMMENTS IN THE IN TROOUC TI ONo 


STA TUS 

LAS CRAMER* - LA-4 4 20 ( 1970). CATA 35 EV TO 2o9 MEVc 

ORL RCSLER+ - LSNOC-1 148(1972), WORK IN PROGRESS 500 KEV TO 8 MEVc 

GEL THEOBALD* - cANCC(E)-157 (1573), IN PROGRESS IN SUBTHRESHOLD REGIONc 


212C62 5C0o 1 5O 0 MEV JoYcEARRE 

A: ACCURACY RELATIVE TO NU CF-252o 


214014 

5o 00 MEV CCP McNcNIKOLAEV FEI 

0: SEE GENERAL COMMENTS IN THE INTRODUCTION 

STATUS 

GA CARLSON* - NP/A 141 577( 1570), DATA THERMAL TO 20 KEV.- 

GEL ROHR+ - EANDC(E)-157 (1973). IN PROGRESS 5 EV TO 2 KEVo 

SGA EDER+ - 73 PARIS PAPER 12. COMPILATICNo 

HAR CABELL* - AERE-R-6761 ( 1 971 >c THEHMALo 

SRL BAUMANN+ - NSE 32 265(1968). 8 PERCENT AT THERMALo 

STATUS- 

IAE MANERO* - REA 10 637(1972). REVIEW, 

92 URANIUM 236 NEUTRON RESONANCE PARAMETERS 

214011 1 Co 0 EV 5o00 KEV 2 CCP McNoNIKOLAEV FEI 

Q: NEUTRON AND CAPTURE WIDTHS WANTED FOR EVALUATION 

OF SELFSHIEL DING IN RESOLVED RESONANCE REGIONc 

A: OBSERVATION OF AT LEAST 50 PERCENT OF P-WAVE 

RESONANCES IN THE ENERGY INTERVAL TO 1 KEV IS 

OESIREOo 

0: SEE GENERAL COMMENTS IN THE INTRODUCTION 

STATISTICAL ANALYSIS OF MEASURED 

RESONANCE PARAMETERS WANTED© 

AVERAGE S AND P WAVE RESONANCE PARAMETERS SHOULD 

BS DERIVED, 


STATUS 

STATUS 

GEL CAFRARO* - 72 EUDAPEST 200. 39 RESCNANCESo 

GEL THEOBALD* - EANOC(E)-157 (1973), IN PROGRESSc 

92 URANIUM 237 NEUTRON CAPTUREE CRoSS licTION 

242380 1o 00 KEV 3,00 MEV 20o OX 1 FR AoMICHAUDON BRC 

0: EVALUATION MAY BE SUFFICIENTc 


242025 lo 00 KEV 15o 0 MEV 20o0X 1 FR Ac MICHAUDON BRC 

O: EVALUATION MAY BE SUFFICIENTo 

STATUS 

STATUS 

USA USNDCo TECHNICALLY VERY DIFFICULT OR IMPOSSIBLE AT PRESENTo 

LAS MC NALLY* - PR/C 9 717(1974), DATA 43 TO 1000 EV AND Oo1 TO 2 MEV FROM NUCLEAR EXPLOSION(POMMARD) 

92 URANIUM 238 NEUTRON TOTAL CROSS SECTION 

212065 5C0o EV 15o0 MEV loOX 2 FR JoYoBARRE CAD 



92 URANIUM 238 NEUTRGN ELASTIC CROSS SECTION 

742061 loOC KEV 15o 0 MEV SoOX FR AoMICHAUDON BRC 

O: FOR CRITICAL ASSEMBLIESo 

92 URANIUM 238 DIFFERENTIAL ELASTIC CROSS SECTION 

651407 1o OC KEV 1 Co 0 MEV CoEoTILL 

Eo HUT CH IN S 

Po BeHEMMIG 

AoMcPERRY 

ANL 

GEB 

AEC 

ORL 

ACCURACY 10 PERCENT FROM 1 TO 3C0 KEVo 

5 PERCENT FROM 300 KEV TO 2 MEVo 

10 PERCENT FROM 2 TO 10 MEVo 

FACTORS OF 2 LOWER ACCURACY WOULD BE USEFUL ON 

SHORT TERMo 

242062 1=00 KEV 1 So 0 MEV SoOX 2 FR AoMICHAUDON BRC 

0: FOR CRITICAL ASSEMBLlESc 

STATUS 

-STATUS 

GEL KNITTER* - ZP 244 358( 1570 1 , DATA lc 5 TO 5oS MEVo 

ANL SMITH* - LSNDC-11 25(1974)o RESULTS TO 4 MEVo 

ABD BUCHER+ - USNDC-11 25(1974). DATA 7 TO 14 MEVc SMALL-ANGLE SCATTERINGc 

GEL KNITTER* - EANCC(E)-1 5 0 (1972). WCRK CONTINUESo 


652262 15o 0 MEV JoYcEARRE CAD 

0: ALTERNATE QUANTITY - NONELASTIC CROSS SECTIONo 


6S236S 8 0o 0 KEV SOOo KEV C HoHAEGGBLOM AE 

A: ACCURACY REQUIRED TO BETTER THAN 10 PERCENTo 

0: NEEDED FOR FAST REACTOR CALCULATIONSo 

6S2333 1 o 20 ME V 2o 00 MEV lOoOX R FoWELLER KFK 

O: LEVEL EXCITATION CROSS SECTIONS FOR THE 45 AND 

148 KEV LEVELS WANTEDo 

242063 1 5o 0 MEV Sc OX AcMICHAUOON BRC 

01 FOR CRITtCAL ASSEMBLIES, 

254021 1 OOo KEV 

1 Oo 0 MEV LoNcUSACHEV FE I 

FROM OO1-0C 8 MEV ACCURACY 4o0 PERCENT, 

PRIORITY 2 ACCURACY 3o4 PERCENTo 

FROM 0o8-lo 4 MEV ACCURACY 4o 0 PERCENT, 

PRIORITY 2 ACCURACY 2o7 PERCENTc 

FROM 1o4-2c 5 MEV ACCURACY 5o 0 PERCENT, 

PRIORITY 2 ACCURACY 3=C PERCENTo 

FROM 2c 5-So C MEV ACCURACY 12 PERCENT. 


FROM 5O0-6O5 MEV ACCURACY 7o 8 PERCENT, 

PRIORITY 2 ACCURACY 7c 0 PERCENTo 

FROM 6o 5-1C MEV ACCURACY 10 PERCENT, 


NEED FOR FAST REACTOR CALCULATIONo 


NEW REOUESTc 

92 URANIUM 238 NEUTRON ANGULAR DIFFERENTIAL INELASTIC CROSS SECTION 

652350 2o CO MEV lOoOX 2 GER FoWELLER KFK 

92 URANIUM 238 NEUTRCN ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

65127C SOoO KEV 

10c 0 MEV SoOX Co EcTILL 

Be HUTCHINS 

PoBcHEMMIG 

ANL 

GEB 

AEC 

0: EMISSION INSTEAD OF INELASTIC AND N.2N MIGHT 

BE USEFULo 

A: ACCURACY OF 20 PERCENT WOULD BE USEFULo 

ENERGY RESOLUTION 5 PERCENTo 


652331 1 So 0 MEV JoY,BARRE CAD 

0: SEPARATION OF LEVELS UP TO 2 MEV REQUIREDo 

A: ACCURACY ON NUCLEAR TEMPERATURE ABOVE 2 MEVo 


632,334 7o 00 MEV 14o 0 MEV SoOX 


92 URANIUM 235 NEUTRON DELAYED N E U T R O N S EMITTED PERFISSION (CONTINUED) 

Z14015 SOOO KEV 15o 0 MEV McN o NIKOLAEV FEI 

DECISION ABOUT TOTAL INELASTIC CROSS SECTION AT 

1 = 0 TO 2o 5 MEV WANTEDc 

TEMPERATURE FOR INELASTIC NEUTRONS WANTED AT THE 

HIGHER ENERGIESc 

SPECTRA AND CROSS SECTION FOR DIRECT INELASTIC 

SCATTERING PROCESSES TO BE INVESTIGATED IN THE 

MEV REGION AS WELL AS DIRECT MECHANISM CONTRIB- 

UTlONSo 


THRESHOLD OF U-238 WANTED TO lo5 - 2o 0 PERCENTo 


THRESHOLD OF PU-240 OR NP-237 WANTED TO 3 - 5 

PERCENT: 

EXCITATION CS FOR FIRST LEVEL ABOVE THRESHOLD TO 2 

MEV SHOULD BE MEASURED WITH 5 PERCENT ACCURACYo 

NEUTRON SPECTRA TO BE MEASURED WITH 5 PERCENT 

ACCURACY AT 2=515 MEVo 

SEE GENERAL COMMENTS IN THE INTRODUCTIONo 

PRECISION MEASUREMENTS OF MENTIONED INTEGRAL 

PARAMETERS IN SHELL TRANSMISSION EXPERIMENTS 

WITH CF-252 NEUTRON SOURCE AND U-238 AND NP-237 

FISSION THRESHOLD DETECTORS AS WELL AS BY 

NEUTRON SPECTROMETER SEEMS VERY USEFULo 

SUBSTANTIAL MOO IF ICAT.I ONSo 

-STATUS 

GEL 

PEL 

HAR 

GEL 

ANL 

KFK 

AE 

L T I 

KNITTER* - ZP 244 358( 1971). DATA 1c 5 TO 2o3 MEVo 

BARNARD* - 70 HELSINKI 2 103. DATA TC lc4 MEVo 

ARMITAGE* - AERE-PR/NP18 (1972). IN PROGRESS lo1 TO 2=4 MEVc 

KNITTER* - EANCC(E)—15G (1972), WCfiK CCNTINUESo 

SMITH* - LSNOC-11 25(1974)o NEW RESULTS TO 4 MEVo 

VOSS* - EANDC(E ) -157 (1973), IN PROGRESS TC 2 MEVo 

CONDE+ - WORK IN PROGRESSo 

MARCELLA* - DATA 1 TO 2o 7 MEVo 

92 URANIUM 238 NEUTRON DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

£52252 1o 00 MEV 2o 50 MEV UK CcGoCAMPBELL WIN 

o: FOR FAST REACTORSc 

65,3062 3 09o KEV 1 Oo 0 MEV lOoOX 1 BAN MoMc ISLAM RAM 


Z420S4 

1 5o 0 MEV SoOX FR AoMICHAUDON 

STA TUS- 

STATUS- 

-STATUS 

HAR ARM ITAGEo - IN FROGRESSo 

92 URANIUM 238 NEUTRON NCN-ELASTIC CROSS SECTION 

65.2.0 £1 ICOo KEV 1Oo 0 MEV lOoOX BAN M0M0ISLAM RAM 


Z1401Z 1 1 Co 0 KEV 1 5o 0 MEV MoNcNIKOLAEV FEI 

DIRECT MEASUREMENTS BY SHELL TRANSMISSION 

DESIRABLE WITH 3-5 PERCENT ACCURACY, 

FOR EVALUATION OF INELASTIC SCATTERING CROSS 

SECTION FOR FAST REACTORSo 

92 URANIUM 238 NEUTRCN CAPTURE CROSS SECTION 

651415 SCO, EV 

1Oo 0 

MEV 

C0E0TILL 

Be HUTC H INS 

P o BeHEMMIG 

ANL 

GEB 

AEC 

ACCURACY 6 PERCENT FROM 500 EV TO 1 KEV, 4 PERCENT 

FROM 1 KEV TO 300 KEV, 6 PERCENT FROM 300 KEV TO 

500 KEV, 10 PERCENT FROM 500 KEV TO 10 MEVo 

ACCURACY OF 10 PERCENT FROM 1 KEV TO 10 MEV, 

USEFULc 

HIGHEST PRIORITY NEED FOR FAST REACTOR 

CALCULATIONSo 

651435 10,0 KEV 

1 Oo 0 MEV 

COECTILL 

BoHUTCHINS 

PoBeHEMMIG 

Ao.M,PERRY 

ANL 

GEB 

AEC 

ORL 

NEEDED IS RATIO OF CAPTURE CROSS SECTION U-238 TO 

FISSION CROSS SECTION OF PU-239 OR U-235o 

DIRECT RATIO NEEDED TO SUPPLEMENT SEPARATE 

MEASUREMENT, 

ACCURACY 1,5 PERCENT BELOW 300 KEV, 7 PERCENT 

ABOVEo 

INTERMEDIATE ACCURACY USEFUL NEAR TERMo 

652401 SoOO MV 

60 00 EV 

J0G0TYROR 

A: ACCURACY REQUIRED o03 BARNSo 


£52402 4,00 EV 500, EV 2,OX HOTELLIER SAC 

0: RELATIVE TO SIGMA(N.G) AT THERMALo 

O: FOR CALCULATION OF IEFFo 

EVALUATION MAY SUFFICE IF IT EXPLAINS 

DISCREPANCIES, 


92 URANIUM 235 NEUTRON D E L A Y E D N E U T R O N S E M I T T E D P E R F I S S I O(CONTINUED) 

N 

692462 500c EV 800c KEV fi hoGERWIN JUL 

A: ACCURACY 2 PERCENT 10 TO 400 KEV, 

3 PERCENT ELSEWHEREo 


£32404 SCOc EV loOO MEV HoTELLIER SAC 

0: RELATIVE TO SIGMA(N.G) AT THERMALo 

0: EVALUATION MAY SUFFICE IF IT EXPLAINS 

D ISCREPANCIE So 

692435 1 Oo 0 KEV 2c 00 MEV CoGcCAMPBELL KIN * 


E AND 2E= 


692406 5o 00 KEV 1o 00 MEV 3c OX SWC Ho HAEGGBLOM AE 

O: NEEDED FOR FAST REACTOR CALCULATIONSc 

693066 2So 3 MV 30o 0 KEV MoMoISLAM RAM 


232032 

1o 00 

KEV 

loOO 

MEV 

So I IJ IMA 

NPG 



PRECISE MEASUREMENT AT SOME ENERGY POINTS ALSO 

DESIREDo 

214022 

SCOo 

EV 

lo 40 

MEV 

MoNc N IKOLAEV 

FE I 

RATIO TO U-235 FISSION CS IS WANTEDo 

ABSOLUTE MEASUREMENTS OR RATIOS TO B-10(N.ALPHA) 

AND LI-6(N,ALPHA) CROSS SECTIONS WOULD ALSO BE 

USEFUL, AND AT HIGHER ENERGIES THE RATIO TO THE 

NP-237 FISSION CSo 

TRANSMISSION MEASUREMENTS WITH FLAT-RESPONSE 

DETECTOR AND BY THE SELF-INDICATION METHOD WITH 

CAPTURE GAMMA-RAY DETECTOR IN THE TEMPERATURE 

RANGE 70-2500 DEGREES K ARE DESIRED FOR EVAL- 

UATION OF SELF-SHIELDING AND DOPPLER EFFECTSo 

SPHERICAL TRANSMISSION TIME-OF-FLIGHT MEASURE- 

MENTS SEEM TO BE A USEFUL INDEPENDENT METHOD 

FOR DETERMINING THE RELIABILITY OF CAPTURE 

CROSS-SECTION DATAo 

BETWEEN 1 AND 100 KEV INFORMATION ON RESONANCE 

SELFSHIELDING FACTORS (SEE BOOK BY ABAGYAN ET 

ALc , CONSULTANTS BUREAU, NEW YORK, 1 964) 

WITH 2 PERCENT ACCURACY AND AVERAGED OVER Oo2 

LETHARGY INTERVALS DESIREOo 

TEMPERATURE DIFFERENCES OF SELF SHI ELD ING FACTORS 

MUST BE KNOWN WITH 7 PERCENT ACCURACYo 

SEE GENERAL COMMENTS IN THE INTRODUCTIONo 

FIRST PRIORITY BECAUSE IT IS DIFFICULT TO 

INTERPRET THE DOPPLER-EFFECT AND SELF-SHIELDING 

FACTORS FROM MACROSCOPIC DATA ONLYo 


241123 loOO EV 2 0o 0 KEV SoOX USA NoSTEEN BET 

0: TO RESOLVE DISCREPANCIES AMONG INTEGRAL AND 

DIFFERENTIAL EXPERIMENTSo 


242562 1o 00 KEV 3o 00 MEV SoOX AoMICHAUDON BRC 

FOR CRITICAL ASSEMBLIESc 

254535 5o 00 KEV lOoO MEV CCP LoNoUSACHEV FE I 

FROM Oo 5 100 KEV ACCURACY 4C 6 PERCENT, 

PRIORITY ACCURACY 2ol PERCENTo 

FROM Oo1 Oo 8 MEV ACCURACY 4o 0 PERCENT. 

PRIORITY ACCURACY 2o 7 PERCENTo 

FROM 0 o 8 4c 5 MEV ACCURACY 9c 6 PERCENT, 

PRIORITY ACCURACY 9o 3 PERCENTo 

ABOVE 4o5 MEV REQUIREMENTS 2 TIMES WEAKERo 


FOR MORE DETAIL SEE INTRODUC TIONo 

NEW REQUESTc 


92 URANIUM 235 NEUTRON D E L A Y E D N E U T R O N S E M I T T E D P E R F I S S I(CONTINUED) 

O N 

HAR 

KFK 

FE I 

CCP 

ANL 

SOWERBY* - ANE 1 409(1974), EVALUATION OF CATA PUBLISHEC BEFORE ABOUT JANUARY 1973c 

o o ES TIMA TEC UNCERTAINTY IN CAPTURE CROSS SECTIONoo 

oo 1 KEV TO 1 CO KEV oooo 6 PERCENT oc 

oo 100 KEV TO 300 KEV oooo 5 PERCENT oo 

=o 300 KEV TO 2 MEV ooco 5 TO 10 PERCENT oc 

oo 2 MEV TO 20 MEV oooo 10 TO 100 PERCENT oo 

FOLLOWING CATA AVAILABLE SINCE SOWEKEY EVALUATION; 

BLUHM - KFK-1758 (1973), DATA 10 KEV TO 5 MEVo 

ChELNOKOV* - YFI-13 6(1972), DATA 230 EV TC 35 KEVc 

STAVISSKY + - AE 31 107(1971), DATA TC 40 KEVc 

POENITZ - LSNDC-1 8(1972), IN PROGRESS 400 KEV TO 1o S MEVo 

ORL 

OE SAUSSURE+ - NSE 51 385(1973) 

PROGRESSo 

DATA 5 EV TO 100 KEV 

ALSO DATA 270 EV TO 500 KEV AND WORK IN 

HAR PEARLSTE IN* - EANDC(UK)-151 (1973), DATA 80 TO 16 CO KEVo 

KFK SPENCER* - NEANDC(E)-161 91 (1974) , 10 TO 600 KEV , IN PROGRESSo 

LRL LINONER* - UCRL-7583 8. DATA 120 KEV TO 2o 9 MEVo 

HAR MOXONo ( 1574). FROVISICNAL DATA AVAII ABLE FROM 5 MV TO 6 EV, ANALYSIS 

BNL RIMAWIo (1574) , CATA AT 24 KEVo 

CAD o (1974) . DATA TO 65 KEVo 

GEL o (1974) . CATA TC 4o1 KEVo 

BNL SEMINAR ON U-2 2E RESONANCE CAPTURE, 18-20 MARCH 75 

92 URANIUM 238 NEUTRON PHOTON PRODUCTION CROSS SECTION IN INELASTIC SCATo 

6S3C62 3 00c KEV 4o CC MEV N Mo Mc ISLAM RAM 

O: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REQUIRED, 


STATUS 

-STATUS 

SUN MC MURRY+ - 72 BUDAPEST 10, CATA 700 KEV TC 109 MEVo 

92 URANIUM 238 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

Z12066 

200o 

KEV 

1 5c OX UK CcGcCAMPBELL WIN 

Q: GAMMA SPECTRUM WANTEDo 



o: FOR STUDY OF ACTIVATION AND HEAT RELEASE IN COREo 

Z210Z.S 

1 5o 0 MEV 

Po Bo HEMM I G 

AEC 

Q: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REQUIREDo 

FOR ALL GAMMA ENERGIESc • 

A: GAMMA-ENERGY INTERVALS - 500 KEVo 

0: FOR SHIELDING AND GAMMA-HEATING CALCULATIONSo 


92 URANIUM 238 NEUTRCN N, 2N 

Z14.Q1.S 20o0 MEV McNcNIKOLAEV FE I 

Q: SECONDARY ENERGY DISTRIBUTION REQUIREDo 

A: ACCURACY 5 TO 10 PERCENT WANTEDo 

ENERGY SPECTRA OF SECONDARY NEUTRONS DESIRABLE 

WITH 5 PERCENT ACCURACY AND Oo2 RESOLUTION IN 

LETHARGYo 

a: FOR FAST REACTORSo 

Z2101B 1 Oo 0 MEV 

BoHUTCHINS 

o: IMPORTANT TO PRODUCTION OF U-238o 


STATUS- 

STATUS- 

ALD MATHER* - AWRE/0-72/72, DATA 7o 0 TO 12 MEVo 

BNW WOLKENHAUER* - 73PARIS 1 39. REVIEW THRESHOLD TO 16 MEVo 

LRL LANDRUM+ - PR/C E 1930(1973). , DATA 14 TO 15 MEVc 

DUB BELOV+ - IJP 47 232(1973), WORK AT 15 MEVo 

BRC FREHAUT+ - CEA-R-4627 (1974),, WORK THRESHOLD TO 15 MEVo 

92 URANIUM 238 NEUTRCN FISSION .CROSS SECTION 

67120 5 SCOo KEV ISo 0 MEV 1 USA GoEoHANSEN LAS 

a: RATIO TO U-235 FISSION WANTEDo 

A: ACCURACY 5 PERCENT TO lo 3 MEV AND 1 PERCENT ABOVEo 

ENERGY RESOLUTION - 3 PERCENTo 

ENERGY CALIBRATION - 1 PERCENT, 

0: FOR FAST BREEDER CALCULATIONSo 

FOR CURIUM AND CALIFORNIUM PRODUCTIONo 

63.1416 1 4o 0 MEV Pc Bo h'EMM IG AEC 

O: RATIO WANTED RELATIVE TO U-235 FISSIONo 

A: ACCURACY 4 PERCENT BELOW 1o3 MEV. 2 PERCENT lo3 TO 

So MEV. 3 PERCENT ABOVE So MEVo 

ENERGY RESOLUTION 3 PERCENT. ENERGY 

CALIBRATION 1 PERCENTo 

INTERMEDIATE ACCURACY USEFULo 



653065 15o C MEV 5o 0X 1 BAN MoMc ISLAM RAM 


212261 2c OX 2 UK CoGoCAMPBELL WIN 

JoGoTYROR 

WIN 

0: FISSION SPECTRUM AVERAGE wAN TE Dc 

O: FOR FAST AND THERMAL REACTOR So 

214220 8C0o KEV 1 5o 0 MEV 1 CCP McNoN IKOLAEV FEI 

0: RATIO TO U-235 FISSION CS IS WANTED, 

ABSOLUTE MEASUREMENTS AND MEASUREMENT OF THE RATIO 

TO THE NP-237 FISSION CS WOULD BE VERY USEFULc 

AVERAGE CS IN FISSION-NEUTRON SPECTRUM OF CF-252 

TIMES NU-BAR OF CF-252 IS OF GREAT INTEREST FOR 

REDUCING THE DEPENDENCE OF THE ACCURACY OF 

NEUTRON PRODUCTION CALCULATIONS UPON THE 

ACCURACY OF' THE CF-252 NU-BAR STANDARD 

(REQUIRED ACCURACY 1 PERCENT >c 

A: REQUESTED ACCURACIES - 5 PERCENT BELOW lc 3 MEV, 

ANC ABOVE 6c 5 MEV, AND 2 PERCENT BETWEEN 

1 , 3 AND 6c 5 MEVc 

ABSOLUTE VALUES WITH 2 TO 3 PERCENT ACCURACYo 

O: SEE GENERAL COMMENTS IN THE INTRODUCTION 

AT LEAST THREE DIFFERENT MEASUREMENTS WITH THESE 

ACCURACIES WANTEDc 

FIRST PRIORITY BECAUSE HIGH ACCURACY OF THE U-236 

FISSION CS IS IMPORTANT IN CONNECTION WITH THE 

USE OF THIS CS AS A CONVENIENT STANDARD FOR 

THRESHOLD-REACTION MEASUREMENTSo 


222112 5o 00 MEV 3c 0 X 1 UK Co Gc CAMPBELL WIN 


742386 15o 0 MEV 3o0X 1 FR AcMICHAUDON BRC 

0: FOR CRITICAL ASSEMBLIcSc 

242112 2o 0 X 1 EUR NEUTRON DOSIMETRY GROUP GEL 

Q: RATIO OF AVERAGE CROSS SECTION IN A U-235 FISSION 

SPECTRUM TO AVERAGE U-235 FISSION CROSS SECTION 

IS WANTEDc 

O: FOR NORMALIZATION OF AVERAGE CROSS SECTIONS FOR 

DOSIMETRY PURPOSESo 

242136 lo 50 MEV 6o 70 MEV SoOX 2 EUR NEUTRON DOSIMETRY GROUP GEL 


METHODSo 


INTEGRAL AND DIFFERENTIAL MEASUREMENTSc 

254519 a OOo KEV 1 Oo 0 MEV 

LoNc USACHEV 

FEI 

FROM Oo 8 - ICoO MEV ACCURACY 2o8 PERCENT . 

PRIORITY 2 ACCURACY lo8 PERCENTo 



NEW REQUESTo 

STATUS- 

HAR SOWERBY+ ANE 1 409(1974), EVALUATION OF CATA PUBLISHED BEFORE ABOUT JANUARY 1973o 

o oESTIMA TEC UNCERTAINTY IN FISSION CROSS SECTIONoo 

oo 600 KEV TO 1 MEV oooo 20 TC 10 PERCENT c o 

oo 2 ME V TO 20 MEV oooo 4,0 TO 5o5 PERCENT oo 

oo NEAR 14 MEV ooooooooooo 2 PERCENT 

FOLLOWING OATA AVAILABLE SINCE SOWERBY EVALUATION 

LRL BEHRENS+ - ISNOC-l1 136(1974). TC 20 MEVc 

RPI BLCCK+ - PPL 31 247(1 973>o SUBTHRESHOLD FISSION 

HAR COATES+ - AERE-PR/NP-21 8(1974), DATA 400KEV TO 22 MEV RELATIVE TO U-235 FISSION CROSS SECTIONo 

KFK BROTZ+ - NEANCC(E)-161 99(1974) , IN PROGRESS 1 TO 30 MEVo 

CCP FUSSOVo - 73KIEV, DATA lo4 TC 70 4 MEVo 

ALCHASOVo - 73KIEV, VALUE AT 1 4o 6 MEVo 

LAS SILBERT* - PR/C 4 220(1971loBOMB DATAo AVERAGE SUBTHRESHOLD CROSS SECTION. 10 KEV TO 100 KEVo 

92 URANIUM 238 NEUTRCN NEUTRONS EMITTED PER FISSION (NU BAR) 

551225 1Oo 0 MEV 1o OX 1 USA CoEoTILL ANL 

Po So HEMMIG 

AEC 

O: ENERGY REOUESTEC IS A MAXIMUM VALUE ONLYo 

RATIO TO CF-252 NU WANTEDo 

O: TO VERIFY MEASUREMENT OF SOLEILACo 


214321 5o 00 MEV 0o7X 2 > MoNoNIKOLAEV FEI 

O: RATIO TO CF-252 NU WANTEDo 

A: ENERGY DEPENDENCE MUST BE KNOWN WITH Oo 7 PERCENT 

ACCURACY AND ABOUT 10 PERCENT ENERGY 

RESOLUTIONo 


242556 15o 0 MEV loOX 1 FR AoMICHAUDON BRC 

0: FOR CRITICAL ASSEMBLIESO 



Z54 020 800c KEV 1 Oc 0 MEV LoNoUSACHEV FEI 

FROM Oo B - lOoO MEV ACCURACY 2o1 PERCENT, 

PRIORITY 2 ACCURACY loO PERCENTo 



NEW REQUEST, 

STATJS- 

-STATUS 

I AE 

LRL 

ANL 

ALD 

MANERO+ - REA 10 637(1572), REVIEWo 

HOWE* - NCSAC-42 130(1971). 1 KEV TO 15 MEV.,IN PROGRESSo 

OAVEY - NSE 44 345( 1971 ). EVALUATION TO 1 5 MEVc 

MATHER* - AWRE-0-44/71, EVALUATION TC 15 MEV 

92 URANIUM 238 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION 

652392 2,00 MEV CoGcCAMPBELL 

J o Go TYROR 

WIN 

WIN 

A: LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGYo 

0: FOR FAST AND THERMAL REACTORSo 

Z41JL22 1 So 0 MEV 

0: DATA STILL DISCREPANTc 


-STATUS 

A I 

HFA 

I AE 

LAS 

ANL 

ALO 

TUTTLEo - NSE £6 37(1975), REVIEW WITH RECCMMENCEO VALUES, 

SHALEV+ - NSE 51 52(1973), FAST REACTOR SPECTRUMo 

MANERO* - REA 10 637(1972). REVIEW Ool TO 15 MEVo 

EVANS* - LSNDC-3 127(1972). REVISED OATA AT 3o1 ANC 15 MEVo 

COXo ANL/NCM-5(1974)o MEASUREMENT ANC EVALUATION, 2 TO 15 MEV, 

MCTAGGART - EANCC(UK)-151(1973), FAST REACTOR SPEC MEASUREMENT IN PROGRESSo 

92 URANIUM 238 NEUTRON ENERGY SPECTRUM OF FISSION NEUTRONS 

652400 2,00 MEV 

COGOCAMPBELL 

WIN 

ACCURACY FOR AVERAGE E', 

ACCURACY 10 PERCENT ON NUMBER OF NEUTRONS 

ABOVE 5o MEV AND BELOW o25 MEVo 

LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGYo 


Z21J.45 

SoOO MEV SoOX Po BeHEMMIG AEC 

o: TO RESOLVE DISCREPANCIES IN EXISTING OATA, 

Z42O0S 15o 0 MEV- 2o 0 X 1 FR Ao MICHAUDON BRC 

O: FOR CRITICAL ASSEMBLIESc 

STATUS 

STATUS 

AE JOHANSSON* - EANDC(OR)-135 47(1974), RELATIVE TO U-235, IN PROGRESSo 

92 URANIUM 238 NEUTRON RESONANCE PARAMETERS 

6S12S& 1=00 EV 20o 0 KEV lOoOX USA Po B,HEMMIG 

CoEcT ILL 

BoHUTCHINS 

PoBc HEMMIG 

AEC 

ANL 

GEB 

AEC 

Q: WANTED TO AS HIGH AN ENERGY AS CAN BE MEASUREDo 

O: NEEDED FOR DOPPLER EFFECT IN FAST REACTORSo 

NEED ANSWERS TO QUESTIONS OF MISSING P-WAVE LEVELS 

AND UNCERTAINTY OF GAMMA WIDTHSo 

692265 2,00 KEV 5o 00 KEV 3oOX C Ho HAEGGBLOM AE 

0: NEUTRON CAPTURE AND FISSION WIDTH NEEDED, 


102025 SoOO EV 4o 00 KEV 2o OX Ho T ELL IER SAC 

FOR RESONANCE SELF SHIELDING ANO OOPPLER EFFECT, 

iiAai* 5c 00 KEV MoNoNIKOLAEV FEI 

OBSERVATION OF VERY WEAK P-WAVE RESONANCES IS 

DESIREDo 

RESOLUTION OF 90 PERCENT OF P-WAVE RESONANCES 

CONTROLLED BY PORTER-THOMAS DISTRIBUTION AND 

LEVEL SPACING DISTRIBUTION AND ALL S-WAVE 

RESONANCES BELOW 5 KEV IS OESIREDo 

CAREFUL IDENTIFICATION OF S AND P WAVE RESONANCES 

NEEDED FOR DETERMINATION OF P WAVE STRENGTH 

FUNCTIONo 

REQUEST CONNECTED WITH PROBLEM OF SELFSHIELDING 

EVALUATION IN UNRESOLVED RESONANCE REGIONo 

ATTENTION TO BE PAID TO THE PROBABLE DIFFERENCE 

BETWEEN THE 1/2 (•) AND 1/2 (-) LEVEL OENSITIESo 

FIRST PRIORITY BECAUSE INVESTIGATION OF THE PARITY 

DEPENDENCE OF LEVEL DENSITY IS OF INTEREST FROM 

A SCIENTIFIC AS WELL AS FROM A PRACTICAL POINT 

OF VIEWo 




Z52115 60CO EV lOo 0 KEV 3oOX 1 UK Co Gc CAMPBELL WIN 

A: ACCURACY IS FOR THE AVERAGE ERROR BETWEEN E AND 

2Ec 

BROAD RESOLUTION MEASUREMENTS COULD SUFFICEo 


TO GIVE SHIELDED CROSS SECTIONS TO 3 PERCENTo 

TO GIVE DOPPLER CHANGE TO 5 PERCENT FOR 

TEMPERATURES BETWEEN 300 AND 1290 DEGREES Ko 

STATUS 

STATUS 

COL RAHN* - USNOC-1 67(1972), 74 P-WAVE RESONANCES, 

DUB MALECKY+ - AE 32 49(1972), DATA TO 102 KEVo 

BNL CHRIEN+ - PR/C 4 900(1971). DATA TO 600 EVo 

RPI B Y0UN+ - LSNDC-3 166(1972). IN PROGRESSo 

HAR SOWERBY* (1974), FEASIBILITY STUDIES RELATED TO REQUEST NUMBER 732113 IN PROGRESSo 


ZA2SSB 1o 00 KEV ISoO MEV 20o0X 1 FR AoMICHAUDON BRC 

o: EVALUATION MAY BE SUFFIClENTo 

93 NEPTUNIUM 237 GAMMA GAUMA.N_ 

69.2465 20 o OX 3 UK AoWHITTAKER UKW 

0: PRODUCTION OF PU-236o 

FOR AN AVERAGE GAMMA RAY ENERGY FROM MG. C, 

ZIRCALOY AND STAINLESS STEEL(20/25)o 

0: FOR ISOTOPE PRODUCT IONo 

9 3 NEPTUNIUM 237 NEUTRON CAPTURE CROSS SECTION 

£.11JU= loOO MV So 00 MEV 1 USA Bo hUTCHINS GEB 

A: ACCURACY - 3 PERCENT FROM THERMAL TO 10 EV. 

10 PERCENT ABOVE 10 EV, 

5 PERCENT IN NEUTRON WIDTH, 10 PERCENT IN GAMMA 

WIDTH FROM THERMAL TO 1 KEVo 

0: ABOVE 1 KEV PRIORITY 20 

FOR THERMAL REACTOR CALCULATIONS AND PU-238 

PRODUCTIONo 


STATUS 

STATUS 

LRL NAGLE+ - 71 KNCXVILLE 259. CATA 100 KEV TC 3 MEVo 

GEL THEOBALD* - EANDC(E)-157 (1973), IN PROGRESS TO 300 EVo 

ANC SMITH* - IN-1162(1969), EVALUATION TO IS MEVo 

93 NEPTUNIUM 237 NEUTRCN N.2N 

621U2 15o 0 MEV lOoOX 2 USA FcJoMC CROSSON SRL 

O: TO EVALUATE CONTAMINATION OF PU-238 BY PU-236o 

651295 1Oo 0 MEV lOoOX 2 USA BoHUTCHINS GEB 

0: NEEDED FOR CONTROL OF U-232 PRODUCT IONo 

STA TUS 

STATUS 

ALD PERK IN* JNE/AB 14 69(1961). DATA AT 19o 5 MEVo 

93 NEPTUNIUM 237 NEUTRON FISSICNCROSS SECTION 

661543 20cC EV SOo 0 KEV lOoOX 3 USA GoEchANSEN LAS 

O: RATIO TO U-235 FISSION WANTEDo 

A: ENERGY RESOLUTION - 30 PERCENTo 

661645 50o 0 KEV lo 00 MEV SoOX 1 USA GoEc HANSEN LAS 

Q: RATIO TO U-235 FISSION WANTEDo 


661646 loOO MEV 15o 0 MEV loOX 2 USA GoEoHANSEN LAS 

O: RATIO TO U-235 FISSION WANTEDo 



95 NEPTUNIUM 237 NEUTRON FISSION CROSS SECTION < CONTINUED) 

STATUS 

STATUS 

K TO KOBAYASHI+ - EANDC(J)-26 (1972). OATA 4,3 TO 4,8 MEVc 

LAS J IACOLETTI+ - LA-4763 (1971), DATA 20 EV TO 7,7 MEV, 

GEL THEOBALD* - EANCC(E)-1 SO ( 1972), IN PROGRESS 1 EV TO 1 KEV, 

NBS BOWMAN* - WORK PLANNED 10 KEV TO 2 MEVc 

CCP GAVRILOV+ - AE 26 362(1970). DATA TO I KEVo 

LAS BROWN* - NF/A 1=6 609(1970). BOMB DATAo 

IAE BAK* - KNS 3 77(1971), EVALUATION TO 19 MEVo 

SAC PAYA+ - EANDC(E)-127U(19 70)o TO 2 KEVo 

NDC SCHETT+ - EANDC-95 (1974). COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY I974o 

NBS BOWMAN* - MEASUREMENTS PLANNED FCR 1975o 

93 NEPTUNIUM 238 NEUTRCN CAPTURE CROSS SECTION 

66-1502 2So 3 MV 2 CAN Wo Ho WALKER CRC 

A: ACCURACY REQUIRED 100 Bo 

o: UNKNOWN CROSS SECTIONo 

93 NEPTUNIUM 239 NELTPCN CAPTURE CROSS SECTION 

212025 1 Co 0 KEV 3c 00 MEV 20o OX 3 JAP MoOHTA KYU 

0: FOR CORRECTION OF CALCULATED INELASTIC SCATTERING 

CROSS SECTIONo 


94 PLUTONIUM 236 NEUTRON FISSICN CROSS SECTION 

212026 25=3 MV 1 5c 0 MEV 10c OX 2 GER EoGOEL KFK 

0: FOR BURN UP CALCULATIONSo 

94 PLUTONIUM 237 NEUTRON CAPTURE CROSS SECTION 

242592 1o 00 KEV 3c 00 MEV 20o OX 1 FR Ac MICHAUDON BRC 

0: EVALUATION MAY BE SUFFICIENTo 


652411 1= 00 KEV 1 So 0 MEV 20o OX 1 FR Ac MICHAUDON BRC 

94 PLUTONIUM 238 NEUTRCN CAPTURE CROSS SECTION 

6 8.1605 25o 3 MV SoOX 2 CAN Wo Ho WALKER CRC 

0: DISAGREEMENT BETWEEN INTEGRAL (APPROX 450 B) AND 

DIFFERENTIAL (APPROX 530 B) MEASUREMENTSo 

252096 500= EV 1o 00 MEV 20o0X 2 FR JoY,BARRE CAD 

0: VALUE RELATIVE TO U-238 CAPTURE CROSS SECTIONo 

O: FOR FAST REACTOR CALCULATIONSO 

242093 1o 00 KEV 3,00 MEV 20o0X 2 FR Ao MICHAUDON BRC 

STATUS 

STATUS 

LAS SILBERT+ - LA-5C24 (1972). CATA 18 EV TO 200 KEVo 

KFK HINKELMANN - KFK-1166(1970). EVALUATION TC 10 MEVo 

94 PLUTONIUM 238 NEUTRCN N.2N 

682062 15o 0 MEV lOoOX 1 FR Ao MICHAUDON BRC 

STATUS 

STATUS 

BRC EXPERIMENT IN FFOGRESSo 

94 PLUTONIUM 238 NEUTRCN FISSICN CROSS SECTION 

662064 1 5o 0 MEV 20o0X 1 

FR Ao MICHAUDON BRC 

0: MEASUREMENTS DONE AT LOS ALAMOS MAY SATISFY THIS 

REQUEST UP TO 1 MEVo 

EVALUATION MAY BE SUFFICIENT 

222095 5C0o EV 15o0 MEV lOoOX 2 

FR 

JoY,BARRE 

CAD 

O: VALUE RELATIVE TO U-235 FISSION CROSS SECTIONo 



94 PLUTONIUM £38 NEUTRCN FISSION CROSS SECTION _ (CONTINUED^ 

STATUS 

STATUS 

ALO MCAT - AWRE/0-13/72. DATA 17 EV TO 1 MEVo 

LAS SIL8ERT - LA-4674 (1571), CATA 18 EV TO 3 KEVo 

LAS DRAKE* - LA-442C(19701. DATA TC 2=6 MEV 

94 PLUTONIUM 238 NEUTRCN NEUTRONS EMITTED PER FISSION (NU BAR) 

HZUai SCOo EV 15o 0 MEV lOoOX 2 FR JoY; BARRE CAD 

0: VALUE RELATIVE TO CF-252 NUo 


94 PLUTONIUM'239 NiuTRCN TOTAL CROSS SECTION 

7ALLSI LOOO EV SOOo KEV 3o OX USA BchUTCHINS GEB 

A: ENERGY RESOLUTION TO SHOW SECONDARY STRUCTURE UP 

TO 10 KEVo 


94 PLUTONIUM 239 NEUTRON ELASTIC CROSS SECTION 

lOoOX Jo Gc TYROR WIN 

Q: THERMAL AVERAGE INCIDENT ENERGY, 

0: FOR LONG TERM IMPROVEMENT OF THE ABSORPTION CROSS 

SECTIONO 

Z42A94 lo 00 KEV 1 5o 0 MEV SoOX FR Ao MICHAUDON BRC 

O: FOR CRITICAL ASSEMBLIESc 

94 PLUTONIUM 239 NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

5S1302 1o 00 MEV 3o 00 MEV lOoOX CcEc TILL 

PoBoHEMMIG 

ANL 

AEC 

A: ENERGY RESOLUTION SCO KEV OR BETTERo 

zsizass 1o 00 KEV 1 5o 0 MEV SoOX FR AoMICHAUDON BRC 


GEL COPPOLA* - ZP 232 286( 1970), DATA 1o 5 TO 5o5 MEVo 

ANL GUENTHER+ - USNDC-3 13(1972), IN PROGRESS TO 4o MEVc 

94 PLUTONIUM 239 NEUTRCN INELASTIC CROSS SECTION 

6S231S 1 5o 0 MEV 25o OX GER EoGOEL KFK 

0: TOTAL INELASTIC OR NONELASTIC CROSS SECTIONo 

zszuai 1 So 0 MEV FR AoMICHAUDON BRC 

0: FOR CRITICAL ASSEMBLIES; 

7 541123 SOOo KEV 5o 00 MEV LoNoUSACHEV FE I 

A: FROM Oc 8 - lo 4 MEV ACCURACY IS PERCENT, 


FROM 1o 4 - 2c 5 MEV ACCURACY 17 PERCENT, 


FROM 2o 5 - So 0 MEV ACCURACY 3? PERCENT. 

PRIORITY 2 ACCURACY 3C PERCENTo 

0: NEED FOR FAST REACTOR CALCULATIONo 


M: NEJ REOUESTc 

94 PLUTONIUM 239 ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

£>£2Q6£ lOoO KEV 

1 Oo 0 MEV 

JAP 

CROSS SECTIONS FOR EXCITATION OF INDIVIDUAL 

LEVELS DESIREDo 


6S2&Z1 

ISoO 

MEV 

o: SEPARATION OF LEVELS UP TO 1 MEV REQUIREDo 

A: ACCURACY 20 PERCENT UP TO lo4 MEV AND 10 PERCENT 

ABOVEo 

ACCURACY ON NUCLEAR TEMPERATURE 10 PERCENTo 

PRIMARY AND SECONDARY ENERGY RESOLUTION 100 KEVo 

ZJL4623 

15o0 

MEV 

Mc N; N IKOL AEV 

FE I 


THRESHOLDS OF U-238 AND OF PU-240 OR NP-237 

DESIRED WITH 10 PERCENT ACCURACYo 

EXCITATION CROSS SECTION FOR LOW LYING LEVELS 

REQUIRED WITH 15 PERCENT ACCURACYo 

SEE GENERAL COMMENTS IN THE INTRODUCTI ONo 

Z21flfl4 lOoO KEV 1Oo 0 MEV Po BeHEMMIG 


S4PLUT0NIUM 239 NEUTRON_ ENERGY DIFFERENTIAL INELASTIC CROSS SECTION (CONTINUED) 

STATUS 

STATUS 

GEL COPPOLA* - ZP 2 32 286(1970), DATA lo9 TO 5o5 MEVo 

ANL GUENTHER* - USNDC-2 .13(1972) , IN PROGRESS TO Ao MEVo 

96 PLUTONIUM 239 NEUTRON DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

652065 3OOo KEV 1 Oo 0 MEV lOoOX 1 BAN MoMc ISLAM RAM 


242035 1 So 0 MEV 20o0X 2 FR AoM1CHAUDON BRC 


94 PLUTONIUM 239 NEUTRON NON-ELASTIC CROSS SECTION 

652562 ICOo KEV 1Oo 0 MEV lOoOX 2 BAN Mo Me ISLAM RAM 



652432 lo 00 KEV 500o KEV 3oOX 2 

SWC Ho HAEGGSLOM AE 

O: NEEDED FOR FAST REACTOR CALCULATIONSo 

633025 25o3 MV 30o 0 KEV 3oOX 2 

BAN MoM:ISLAM RAM 


202033 lo 00 KEV 200o KEV 5oOX 1 

JAP SoKATSURAGI JAE 

O: ALPHA ALSO USEFULc 


212662 30oC KEV 1 So 0 MEV lOoOX 2 

GER BoGOEL KFK 

0: ALPHA ALSO USEFULc 

A: PREFER 5 PERCENT ACCURACY UP TO 100 KEVo 

0: FOR BURNUP CALCULATIONSo 

242104 loOO KEV 3o CO MEV SoOX 1 

FR AoMICHAUOON BRC 


254012 SoOO KEV 1 Oo 0 MEV 1 

CCP LoNoUSACHEV FEI 

A: FROM Oc 5 - 100 KEV ACCURACY 4o5 PERCENT, 


FROM Oc1 - Oc 8 MEV ACCURACY 10 PERCENT, 


FROM 0 o 8 - 4o 5 MEV ACCURACY SO PERCENT, 


ABOVE 4o 5 MEV REQUIREMENTS 2 TIMES WEAKERo 

0: NEED FOR FAST REACTOR CALCULATIONSc 

FOR MORE DETAIL SEE INTROOLCTIONo 


STATUS 

FEI CHELNOKOVt - YFI-13 6(1972), DATA 200 EV TC 12 KEVo 

ORL GWIN* - NSE 45 25(1971), DATA THERMAL TO 30 KEVc 

ORL WESTON* - LSNDC-3 149(1972). WORK IN PROGRESSo 

HAR SCHOMBERG* - 70HELSINKl 1 315o 100 EV TO 30 KEVo 

94 PLUTONIUM 239 NEUTRON PHOTON PRODUCTION CROSS SECTION IN INELASTIC SCATo 

632353 3G0o KEV 4o OC MEV 1 Co OX 1 BAN MoMoISLAM RAM 

Q: SECONDARY ENERGY-ANGLE DISTRIBUTIONS REOUIREDo 

o: FOR FAST REACTORSo 

STATUS 

STATUS 

LAS DRAKE* - NSE 4C 294(1970). DATA 4 TO 7o7 MEVc 

94 PLUTONIUM 239 NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

652415 120o KEV 20o0X 2 UK CoGcCAMPBELL WIN 

O: GAMMA SPECTRUM WANTEDc 



O: FOR STUDY OF ACTIVATION AND HEAT RELEASE IN COREc 

242056 loOO KEV ISoC MEV lOoOX 1 FR Ao MICHAUDON BRC 

0: FOR SHIELOINGo 


652062 15o 0 MEV lOoOX 1 FR Ao MICHAUDON BRC 

651306 6c00 MEV 1Oo 0 MEV lOoOX 2 USA P o Be HEMMIG AEC 

o: NEEDED TO PREDICT BUILDUP OF PU-236o 

FISSION LIST PAGE 1Io 86

94 PLUTONIUM 239 NEUTRCN N,2N (CONTINUED) 

STATUS 

STATUS 

ALD MATHER+ - AWREZO-72/7 2. IN PROGRESS 6 TO 13 MEVo 


66206.8 1 So 0 MEV 20o0X 1 FR AoMICHAUDON BRC 

STATUS 

STATUS 

ALD MATHER* - AWRE/0-72/72, IN PROGRESS 6 TO 13 MEVo 


661.0 4S 1 Oo 0 KEV ISoO MEV 1 o 0 X USA GoEcHANSEN LAS 

RELATIVE TO U- 235C 

ENERGY RESOLUTION 3 PERCENT. ENERGY 


631439 1o 00 EV 1 Co 0 MEV BoHUTCHINS GEB 

PRIORITY ENERGY RANGE 

ACCURACY 

1 1 EV TO 10 KEV 3 PERCENT 

2 10 KEV TO 1 MEV 2 TO 5 PERCENT 

1 1 MEV TO 10 MEV 5 PERCENT 

VERIFICATION OF CURRENT ACCURACY OR INTERMEDIATE 

ACCURACY USEFUL; 

NEED RELATED ACCURACY FOR 5-10 PERCENT ENERGY BINS 


NEW REOUESTc 

691467 1o 00 EV 1Oo 0 MEV 

COECTILL 

Po Bo HEMMIG 

ANL 

AEC 

A: ACCURACY 3 PERCENT BELOW 20 KEV, 2 PERCENT, 20 KEV 

TO 3 MEV, E PERCENT, 3 MEV TO 10 MEVo 

O: HIGHEST PRIORITY FOR FAST REACTOR CALCULATIONSo 

692426 lo 00 MEV 5o 00 MEV 

CoGoCAMPBELL 

WIN 

0: RATIO TO U-235 FISSION CROSS SECTION ACCEPTABLEo 


E AND 2EC 

o: FOR FAST REACTORSO 

M: MODIFIED (PARTIALLY FULFILLEDLO 

693076 2So 3 MV 15o 0 MEV MoMoISLAM RAM 


714024 lo 00 KEV 4o 00 MEV CCP MoNoNIKOLAEV FE I 

RATIO TO U-235 FISSION CS IS WANTED BUT ABSOLUTE 

MEASUREMENT AND MEASUREMENT OF RATIOS TO B-l0 

(N. ALPHA) . L I-6(N, ALPHA ) CROSS SECTIONS AND 

OTHER STANDARDS WOULD BE VERY USEFULo 

BELOW 30 KEV MEASUREMENTS OF TRANSMISSION CURVES 

BY FLAT RESPONSE DETECTOR AND BY SELF DETECTION 

METHOD WITH FISSION DETECTOR WANTED FOR 

SELFSH1ELOING EVALUATIONo 

THESE CURVES MUST BE MEASURED WITH ATTENUATITNS OF 

THE PRIMARY BEAM DOWN TO 1 PERCENTo 

ACCURACY REQUIRED TO BETTER THAN 2o 0 PERCENTo 

OPTIMUM PRECISION OF 10 5 PERCENT DESIRED IN 

REGION 2C KEV TO 1 MEVo 

LETHARGY RESOLUTION OF ABOUT 0o2 CONSIDERED 

SUFFICIENT FOR SUCH MEASUREMENTSo 

SEE GENERAL COMMENTS IN THE INTRODUCTION, 

REQUEST CONSIDERED FULFILLED, WHEN AT LEAST THREE 

MEASUREMENTS WITH DIFFERENT METHODS AGREE WITHIN 

REQUESTED ACCURACYo 


INTERPRET THE SELF-SHIELDING FACTORS FROM 

MACROSCOPIC DATA ONLYo 

SUBSTANTIAL MOO I F ICA T ION So 

721065 2So 3 MV lo 00 KEV 

BoHUTCHINS 

GEB 

DIRECT MEASUREMENTS DISAGREEo 

IMPROVED PRECISION NEEDED FOR THERMAL REACTORSo 

U AND PU HALF LIVES SHOULD BE CONFIRMED AS THEY 

AFFECT THIS MEASUREMENTo 


221066 1 Oo 0 KEV 14o 0 MEV 

Po Bo HEMMIG 

AEC 

Q: RELATIVE TO U-235c 

AVERAGES OVER 10 TO 20 PERCENT ENERGY INTERVALS 

WANTEDo 

A: ENERGY RESOLUTION 3 PERCENT, ENERGY 


241125 1Oo 0 KEV lo 00 MEV 

BoHUTCHINS 

0: RATIO TO U-235 (N.F) WANTEDo 


242606 lo 00 KEV 5o00 MEV SWC Ho HAEGGBLOM 

A: ACCURACY 2 PERCENT TO 1 MEV, 

0: FAST REACTOR CALCULATIONSo 


242635 1 So 0 MEV AoMICHAUDON BRC 

A: ACCURACY 5 PERCENT TO 1 KEV. 2 PERCENT ABOVEo 

0: FOR CRITICAL ASSEMBLIES, 


54 PLUTONIUM £39 FISSION CROSS SECTION (CONTINUED) 

Z5420S SoCO KEV 1 Oo 0 MEV LoNcUSACHEV FE I 

FROM 0o 5 - 100 KEV ACCURACY 2o8 PERCENT, 


FROM Oc1 - 0 c 8 MEV ACCURACY 3o0 PERCENT. 


FROM OoS - 4o 5 MEV ACCURACY 4o 0 PERCENT, 


ABOVE 4c5 MEV REQUIREMENTS 2 TIMES WEAKERo 



NEW REQUEST, 

HAR SOWERBY+ - ANE 1 4C9(1574). EVALUATION OF CATA PUBLISHED BEFORE ABOUT JANUARY 1973c 

o o ESTIMATED UNCERTAINTY IN FISSION CROSS SECTIONoo 

oo 100 EV TO 3C KEV oooo 3 TO 4 PERCENT cc 

CO 30 KEV TO ICC- KEV oooo So 5 PERCENT oo 

oo 100 KEV TC 3 MEV oooo 4o 0 TC ScS PERCENT oo 

CO 3 MEV TO 2C MEV oooo So 5 TO 10 PERCENT oo 

oo NEAR 14 MEV cooooocoooo 2 PERCENT oo 

FOLLOWING CATA AVAILABLE SINCE SCWERBY EV ALUATIONo 

SAC BL0NS - NSE 51 120(1973), CATA 39 EV TO 30 KEVo 

FEI CHELNOKOV* - YFI-13 6(1972), DATA 200 EV TC 35 KEVo 

LRL BcHRENS* - LSNDC-11 136(1974). IN PROGRESS CoOl EV 100 KEV AND 10 KEV TO 20 MEVo 

GEL THEOBALD* - EANDC(E)-150 (1972). IN PROGRESS 50 EV TO 2 KEVo 

HAR GAYTHER+ - AERE-PR/NP15( 1572), IN PROGRESS 1 KEV TO 1 MEVo PRELIMINARY DATA A VAILABLE o 

ORL G W IN • - USNCC-2 149(1572). IN PROGRESS THERMAL TO 200 KEVo 

NBS BOWMAN - WCRK FLANNEOo 

94 PLUTONIUM 239 NEUTRON CAPTURE TO FISSION RATIO (ALPHA) 

6S1314 100c EV 1 Co C MEV 1 USA CoEoTlLL ANL 

BoHUTCHINS 

GEB 

PoBcHEMMIG 

AEC 

FoCoMAIENSCHEIN ORL 

a: CAPTURE CROSS SECTION EQUALLY USEFULo 

A: ACCURACY ICO EV TO 1 KEV, 8 PERCENT, 

oc 1 KEV TO 50 KEV, 4 PERCENT, 

o; 50 KEV TO 600 KEV. 6 PERCENT, 

o: 60C KEV TO 10 MEV, 10 PERCENTo 

Z.02035 500c EV loOO MEV 5cOX 2 FR JoYoEARRE 

ABSOLUTE VALUES USEFUL BUT REQUEST CONCERNS MAINLY 

RELATIVE VALUES VERSUS ENERGYo 


Z12DZe 2 Oo 0 KEV 1 OOo KEV lOcOX 3 UK Co'Go CAMPBELL 


E AND 2Ec 

O: FOR FAST REACTORSO 

Z14225 1OCo EV SOOo KEV 7oOX 1 CCP MoNoNIKOLAEV FEI 

FOR EVALUATION OF DIFFERENCES IN CAPTURE AND 

FISSION-RESONANCE SELF SHIELD INGo 

MEASUREMENTS OF TRANSMISSION CURVES WITH FLAT- 

RESPONSE DETECTOR AND BY SELF-INDICAT I ON METHOD 

WITH CAPTURE AND FISSION DETECTORS ARE WANTEOo 

BEAM ATTENUATION DOWN TO 1 PERCENT WANTEDo 

IN REGION 1 TO 100 KEV, 4 TO 5 PERCENT ACCURACY 

DES IRABLEc 

LETHARGY RESOLUTION OF 0o2 SUFFICIENT FOR REGION 

0:1 TO 30 KEVo 

AT LEAST THREE DIFFERENT REQUESTS MUST COINCIDE 

WITHIN REQUESTED ACCURACYo 

SEE GENERAL COMMENTS IN THE IN TRODUC TI ONo 


INTERPRET THE SELF-SHIELDING FACTORS FROM 

MACROSCOPIC DATA ONLYc 


STA TUS 

STATUS 

FEI CHELNOKOV+ - YFI-13 6(1672), DATA 200 EV TO 12 KEVo 

FEI KONONOV+ - AE 32 85(1972). DATA 10 KEV TO 1 MEVo 

KUR VOROTNIKOV+ - 73KIEV 4 42, DATA 3 TO 200 KEVc 

DUB BOLOTSKII+ - 73 KIEV 4 49, DATA THERMAL TO 30 KEVo 

ORL WESTON* - LSN0C-7 179(1973). IN PROGRESS THERMAL TO 20 KEVo 

KFK BANDL* - EANDC(E)-157 (1573). IN PRCGRESS 8o1 TO 60 KEVo 

ORL GWIN+ - NCSAC-42 159(1971). THERMAL TO 400 KEVo 

ANL KATO* - NSE 45 37(1971). FAST REACTOR SPECTRUMo 

KAP EILAND* - NSE 44 180(1971), PILE SPECTRUMo 

94 PLUTONIUM 239 NEUTRCN NEUTRONS EMITTED PER NEUTRON ABSORPTION (ETA) 

642206 1 Oo 0 MV Oo 50 EV 0c8X 1 

UK JoGoTYROR WIN 

a: VALUE RELATIVE TO 25o3 MV ETA WANTEDo 

A: ACCURACY IS FOR AVERAGE VALUES IN 20 MV STEPSo 

O: FOR TEMPERATURE COEFFICIENT WORKo 

621124 2 5o 3 MV loOO EV OoSX 1 

USA BoHUTCHINS GEB 

0: FOR PU-FUELED REACTOR CALCULATIONSo 

FISSION LIST PAGE Ho 88

94 PLUTONIUM 239 NEUTRONS EMITTED PER FISSION (NU BAR) 

661062 1Oo 0 MEV Cc co T ILL 

Bo hUTCHINS 

Po BoHEMMIG 

AoMoPERRY 

ANL 

GEB 

AEC 

ORL 

0: MEASUREMENT SHOULD INCLUDE LOW ENERGY NEUTRONS 

(TO APPROXIMATELY 1 CO KEVIo 

A: ACCURACY 1 KEV TO 3 MEV, OoS PERCENT, 

OTHERWISE 1 PERCENT, 

ACCURACY OF 1,5 PERCENT WOULD BE USEFULc 

REQUIRE RESOLUTION OF SIGNIFICANT STRUCTURE UP TO 

500 KEV, 

0: HIGHEST PRIORITY FOR FAST REACTOR CALCULATIONSo 

Z02037 1 5o 0 MEV 

ACCURACY REQUIRED TO BETTER THAN 

FOR FAST REACTORS CALCULATIONSo 

C-,5 

PERCENTo 

114026 2o 50 MEV 

MoN,NIKOLAEV 

FEI 

o: 

M: 

RATIO TO CF-252 NU REQUIREDo 

ABSOLUTE MEASUREMENTS OF NU-BAP AND ETA FOR 

THERMAL NEUTRONS WITH ACCURACY OF AT LEAST Co 5 

PERCENT WOULD BE VERY USEFUL FOR LOWERING THE 

DEPENDENCE OF PU-239 NU-BAR RESULTS FROM THE 

CF-252 NU-BAR STANDARDo 

ENERGY DEPENDENCE OF NU IS WANTED WITH Oo 7 

PERCENT ACCURACY, 

ENERGY RESOLUTION OF 10, PERCENT REQUIRED BELOW 

2; 5 MEV; 

SEE GENERAL COMMENTS IN THE INTRODUCTION, 

SUBSTANTIAL MODIFICATIONS, 

142101 1 5o 0 MEV Ao MICHAUDON 

A: ACCURACY 2 PERCENT TO 1 KEV, 


1 PERCENT ABOVE, 

154011 So 00 KEV 1 Oo 0 MEV LoNcUSACHEV FEI 

o: 

M: 

FROM OoS - 100 KEV ACCURACY lo 2 PERCENT , 

PRIORITY 2 ACCURACY Oo 5 PERCENT, 

FROM Oo1 - Co S MEV ACCURACY lcC PERCENT, 

PRIORITY 2 ACCURACY C-,5 PERCENTo 

FROM OoS - 405 MEV ACCURACY 2c1 PERCENT, 


ABOVE 4,5 MEV REQUIREMENTS 2 TIMES WEAKERo 

NEED FOR FAST REACTOR CALCULATIONSc 


NEW REQUESTc 

I AE 

CCP 

BRC 

MANERO* 

VOLODIN* 

FREHAUT+ 

REA 10 £37(1572). REVIEWo 

LRL HO WE + - 

IN PROGRESS THERMAL TO I5 MEVO 

RPI REED* - 

ORL 

WESTON* 

FR/C 10 1402(1974), DATA FCR RESOLVED RESONANCES IN RANGE 10 TO 170 EVc 

94 PLUTONIUM 239 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION 

6S1212 5=00 MEV Co E, T ILL 

Po Bo HEMMIG 

ANL 

AEC 

Q: NEUTRON SPECTRUM WANTED; 

YIELD, HALF LIFE, AND ENERGY NEEDEDo 

0: NEEDED FOR ANALYSIS OF FAST CRITICALS AND FAST 

REACTOR CALCULATIONSo 

Z22.114 

1 OOo KEV Co Gc CAMPBELL WIN 

A: LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGYc 


STA TUS- 

STATUS- 

A I 

ANL 

FEI 

HFA 

KFK 

LAS 

LAS 

FEI 

I AE 

TUTTLEo - NSE 5 6 37(1975). REVIEW WITH RECOMMENCED VALUESo 

COXo - ANL/NOM-5 (1974). MEASUREMENTS ANC REVIEW. 2 TO 15 MEVo 

TARASKO+ - YF 17 1149(1973). IN THERMAL ANC FISSION SPECTRUMo 

SHALEV+ - NSE 51 52(1973). THERMALo 

FI EG - EANCC(E)-157(1973), AT 14 MEV, IN PROGRESSo 

EVAN St - LSNDC-3 127(1972). Oo1 TO 15 MEV. REVISEO 

KRICK+ - NSE 47 311(1972), Ool TO loS MEVo 

MAKSJUTENKO* - YFI-10 27(1971), IB TC 21 MEVo 

MANERO+ - REA 10 637(1972), REVIEWo 

94 PLUTONIUM 239 NELTRCN ENERGY SPECTRUM OF FISSION NEUTRONS 

6S2S22 ICOo KEV 2oOX CoGoCAMPBELL 

Ac W H ITT AK ER 

ScB: WR IGHT 

WIN 

UK W 

HAR 

ACCURACY 2 PERCENT AVERAGE E•, 

10 PERCENT ON THE NUMBER OF NEUTRONS ABOVE 5 MEV 

AND BELOW o25 MEVo 

LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGYo 

FOR FAST REACTORSo 

FOR REACTION RATE ANALYSISo 


94 PLUTONIUM 239 NEUTRON ENERGY SPECTRUM OF FISSION NEUTRONS (CONTINUED! 

21ZSBQ 2 So 3 MV 2 JAP To I IJ IMA JAE 

A: ACCURACY OF NUCLEAR TEMPERATURE FOR MAXWELL 

DISTRIBUTION IS REQUIRED WITHIN 30 KEVo 


242103 15o0 MEV loOX 1 FR AoMICHAUDON BRC 


STATUS 

STATUS 

KFK WERLE* - JNE 26 165(1972), DATA 100 KEV TC 10 MEVo 

ANL SMITH - ANL-7910 18(1972), DATA 300 KEV TO 8 MEVo 

HAR ADAMS* - (1974), PRELIMINARY DATA AVAILABLE, WORK CONTINUESc 

94 PLUTONIUM 239 NEUTRON FISSICN PRODUCT MASS YIELD SPECTRUM 

62-1125 NcSTEEN BET 

CUMULATIVE AND DIRECT YIELD OF XE-135 INCLUSIVE OF 

15 MINUTE ISOMER IS WANTEOo 


621126 2 Eo 3 MV 1 oOX No STEEN 

FoJoMC CROSSON 

o: 

o: 

BET 

SRL 

FISSION PRODUCT YIELD OF CS-137 WANTEDo 

FOR BURN UP INDICATOR STANDARDo 

621126 2 So 3 MV A NCSTEEN BET 

Q: FISSION PRODUCT YIELD OF NO-147 AND SM-149 WANTEDo 


2116Q3 2 So 3 M V Wo HoWALKER CRC 

Q: 

o: 

YIELD OF XE-135 WANTEDo 

FOR CALCULATION OF FISSION PRODUCT ABSORPTIONo 

241126 1 So 0 MEV 

Eo HUTCH INS 

Q: ALL FISSION PRODUCTSO 


STATUS- 

KUR 

AE 

SRE 

CCP 

CCP 

MILLER* - SJA 27 2 81 (196 9)c 

FORSYTH* - 70 KARLSRUHE VCLol Po521c 

HILLER - KT 12 485(19701= 

GRECHUSHKINA - TABLES SHOWING THE CCMPGSITION OF PROMPT FISSION PRODUCTS FROM U-235, U-238 AND 

PU-23 9 FISSICN. ATCMIZCAT, MOSCCW(1964)o 

GUSEV - PROTECTION AGAINST GAMMA RADIATION FROM FISSION PRODUCTS. ATOM IZOA T. MOSCOW(1969)o 

CCP 

SGA 

HAR 

GRE 

CRC 

GEV 

ANL 

GRESHILOV* - PRODUCTS CF PROMPT FISSION OF U-235, U-238, 

MO SCOW(1565)o 

LAMMER+ - 73 PARIS PAPER 13, EVALUATIONo 

CROUCH - 73 PARIS PAPER 94, EVALUATICNo 

DEVILLERS* - 73 PARIS PAPER 63, EVALUATION 

WALKER - 73 PARIS PAPER 34, EVALUATICNo 

MEEK* - NEOO-121E4, EVALUATIONo 

GLENDENIN* - (1974), WORK IN PROGRESSo 

AND PU-239 FROM 0 TO 1 HOUR. A TOM IZDAT * 

94 PLUTONIUM 239 NEUTRCN RESONANCE PARAMETERS 

651515 600o EV lOoOX 2 USA CoEsTILL ANL 

. Po Be HEMMIG AEC 

BoHUTCHINS 

GEB 


TO DETERMINE STATISTICAL PARAMETERS FOR 

EXTRAPOLATION TO HIGHER ENERGIES FOR FAST 

REACTORSo 

M: SUBSTANTIAL MOO IF ICATIONSo 

692415 250o EV 1o 00 KEV 3oOX 2 SWC Ho HAEGGBLOM AE 

Q: NEUTRON, CAPTURE AND FISSION WIDTH NEEDEDo 


STATUS 

ORL GWIN* - ORNL-47C7 (19711. PARAMETERS FOR 48 RESONANCES? 

STATUS 

94 PLUTONIUM 240 NEUTRCN TOTAL CROSS SECTION 

6S2435 1Oo 0 KEV 1o 00 MEV lOoOX 2 GER BoGOEL KFK 

A: BETWEEN 10 AND 100 KEV AT 1 NSZM RESOLUTIONo 

STATUS 

STATUS 

RPI HOCKENBURV* - 72 BUDAPEST 224. DATA VJP TG 30 KEVo 

FISSION LIST PAGE lie 90

94 PLUTONIUM 240 NEUTRON INELASTIC CROSS SECTION 

221052 1, 50 MEV 1Oo 0 MEV 20,OX 2 USA EoHUTCHINS GEB 

P o Bo HEMMIG 

AEC 

0: EMISSION CROSS SECTION MIGHT BE EQUALLY USEFUL 

AT THE HIGHER ENERGlESo 

94 PLUTONIUM 240 NEUTRCN . iNEKGY DIFFERENTIAL INELASTIC CROSS SECTION 

2.14025 5o 00 MEV 1 Oo OX 2 CCP MoNoN IKOLAEV FEI 

A: CROSS SECTION FOR INELASTIC REMOVAL BELOW FISSION 

THRESHOLDS OF u-238 AND PU-240 OR NP-237 WANTED 

WITH 10 PERCENT ACCURACYo 

EXCITATION CS FOR LOW-LYING LEVELS REQUIRED WITH 

ACCURACY OF IE PERCENT, 

O: SEE GENERAL COMMENTS IN THE INTRODUCTION, 


STATUS 

STATUS 

ANL SMITH* - NSE 47 19( 1972). OATA TC lo 5 MEVo 

94 PLUTONIUM 240 NEUTRCN DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

652442 4o 00 MEV 40 o 0 X 2 UK CoGo CAMPBELL WIN 


94_PLUT0NIUM_240 NEUTRCN_ CAFTURECROSSSECTJON 

621154 25o 3 MV 1OOo EV 3o OX 1 USA BcHUTCHINS GEB 

0: IMPROVED PRECISION NEEDED FOR THERMAL REACTORSo 

652021 1Oo 0 KEV 15,0 MEV lOoOX 1 JAP SoKATSURAGI JAE 

Q: RESONANCE PARAMETERS ALSO REQUIREDo 



65155.5 500o EV 150o KEV SoOX 1 USA CoEcTILL ANL 

A: ACCURACY OF 15 PERCENT USEFULc 

0: HIGH PRIORITY FOR FAST REACTOR CALCULATIONS, 

652451 SCO, EV lo 00 MEV lOoOX 2 FR JoYoBARRE CAD 

0: ABSOLUTE VALUES USEFUL BUT REQUEST CONCERNS MAINLY 

RELATIVE VALUES VERSUS ENERGY OR RELATIVE VALUES 

TO U-238 CAPTURE OR U-235 FI SSIONo 

A: ACCURACY 1 PERCENT ON THIS RATIOO 


MOST RECENT RESULTS ARE DISCREPANT, 

652452 lo 00 KEV 500o KEV lOoOX 2 SWC Ho HAEGGBLOM AE 

A: ENERGY DEPENDANCE WITHIN 10 PERCENTo 


652455 5,CO KEV 1,00 MEV 1 OoOX 2 GER Ec GOEL KFK 

A: 1 NS/M RESOLUTION NEEDED, 

214032 5OOo EV 1 o 40 MEV 7«0X 2 CCP MoNc N IKOLAEV FEI 

Q: RATIO TO U-235 FISSION CS WANTED BUT RATIOS TO 

B-10. L1—6. HE-3 AND OTHER STANDARDS WOULD BE 

VERY USEFULo 



221132 150o KEV lo 00 MEV lOoOX 1 USA BoHUTCHINS GEB 

Po Bo HEMMIG 

AEC 

A: ACCURACY OF 15 PERCENT USEFULo 

o: HIGH PRIORITY FOR FAST REACTOR CALCULATIONSo 

254006 SoOO KEV 1Oo 0 MEV 1 CCP LoNoUSACHEV FEI 

A: FROM OoS - 100 KEV ACCURACY 7o 1 PERCENT. 

PRIORITY 2 ACCURACY 7oO PERCENT, 

FROM 0,1 - OoS MEV ACCURACY 14 PERCENT, 


FROM 0,8 - 4,5 MEV ACCURACY 46 PERCENT. 

PRIORITY 2 ACCURACY 46 PERCENTo 


o: NEED FOR FAST REACTOR CALCULATIONSo 



STA TUS 

STATUS 

RPI HOCKENBURY* - NSE 49 153(1972), PREVIOUS DISCREPANCIES RESOLVED, 

HAR MOXON* - AERE-FR/NP-19 (1972). WORK IN PRGGRESSo 

ORL WESTONo (1574). DATA TC 100 KEVo 

LAS HUNTER* - LA-5172 (1973). EVALUATION, 40 KEV TO 17 MEV, 


94 PLUTONIUM 24C NEUTRON TOTAL PHOTON PRODUCTION CROSS SECTION 

652442 1 2Co KEV 20o0X 3 UK C o G; CAMPBELL WIN 

0: GAMMA SPECTRUM WANTEDo 



O: FOR STUDY OF ACTIVATION AND HEAT RELEASE IN COREc 

94 PLUTONIUM 240 NEUTRON FISSION CROSS SECTION 

621-130 1o 00 KEV ISo 0 MEV USA Go Ec HANSEN LAS 

o: RATIO WANTED RELATIVE TO U-235o 

214C30 lOOo KEV Sc 00 MEV 

McNcNIKOLAEV 

FEI 

0: 

M: 

RATIO TO U-235 OR NP-237 FISSION CS WANTEDo 

MEASUREMENT OF AVERAGE CS IN FISSION-NEUTRON 

SPECTRUM OF CF-252 TIMES NU-BAR OF CF-252 WITH 

ACCURACY OF 2 PERCENT IS DESIREDo 



221088 SCOo KEV 1 Oc C MEV Be hUTCHINS GEB 

IMPORTANT FOR FAST REACTOR CALCULATIONSo 

221085 SCOo EV 1 OOo KEV Po Bo HEMMIG AEC 


221050 loOO KEV 100c KEV Po Be HEMMIG AEC 

RATIO WANTED RELATIVE TO U-235o 

221051 1 OOc KEV 5o 00 MEV PoB3 HEMMIG 

0: RATIO WANTED RELATIVE TO U-235c 


232008 5o 00 MEV lOoOX HoHAEGGBLOM AE 


242022 1 o 00 KEV 

1 So C MEV SoOX 1 GER 

Bo GOEL 

KFK 

242105 1o 00 KEV 

1 5o 0 MEV 3oOX 2 FR 

AcMICHAUDON 

BRC 


254003 5o OC KEV 1Oo 0 MEV L0N0USACHEV FEI 

STATUS 

RPI HOCKENBURY+ - NSE 49 153(1972), DATA 20 EV TO 30 KEVc 

HAR BELCHER+ - AERE-PR/NP19 (1972), IN PROGRESS TO 1 MEVo 

KFK CIERJACKS* - EANDC(E)-157 (1973). IN PROGRESS 08 TO 30 MEVo 

ORL WESTON* - LSNDC-7 179(1973). IN PROGRESS THERMAL TO 20 KEVo 

.LRL BEhRENS* - MEASUREMENT PLANNED FCR 1975o 

FROM Oo 1 Oc 8 MEV ACCURACY So 4 PERCENT , 

PRIORITY ACCURACY' 5o3 PERCENTo 

FROM O08 4c 5 MEV ACCURACY 4oC PERCENT, 

PRIORITY ACCURACY 3c 5 PERCENTo 



FOR- MORE DETAIL SEE IN TRODUC TI ONo 

NEW REQUESTo 

94 PLUTONIUM 240 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR) 

652446 5o 00 MEV UK Co Go CAMPBELL WIN 


652446 500o KEV 

1 So 0 MEV 

SoOX 

GER 

714031 

5o 00 

MEV 

1 o 0 X 

CCP MONC NIKOLAEV FEI 

O: RATIO TO CF-252 NU-BAR WANTEDo 



221AS2 

1Oo 0 

MEV 

CoEcTILL 

Po Bo HEMMIG 

ANL 

AEC 

A: ACCURACY OF 5 PERCENT WOULD BE USEFULo 

242106 1o 00 KEV 1 5o 0 MEV AoMICHAUDON BRC 

FOR CRITICAL ASSEMBLIESo 

254004 5o 00 KEV 1 Oo 0 MEV L0N0USACHEV FEI 

O: 

M: 

FROM Oo1 - O08 MEV ACCURACY 3o0 PERCENT, 


FROM Oo 8 - 4o 5 MEV ACCURACY 20 3 PERCENT, 





NEW REQUESTo 


94 PLUTONIUM 240 NEUTRCN _ NEUTRONS EMITTEO PER FISSION (NU BAR)_ _ (CONTINUED) 

STATUS 

STATUS 

IAE MANERO* - REA 10 637(1972). REVIEWc 

BRC FREHAuT* - 73KIEV. OATA 1„5 TO 20 MEVo 

94 PLUTONIUM 240 NEUTRCN ENERGY SPECTRUM OF FISSION NEUTRONS 

Z22055 1 So 0 MEV 3oOX 2 FR JoYo BARRE CAD 

A: ACCURACY FOR AVERAGE E • RELATIVE TO AVERAGE E • 

U-235 OR PU-239o 

94 PLUTONIUM 240 NEUTRCN RESONANCE PARAMETERS 

6S1231 1 OOo EV 5o 00 KEV ICoOX USA CoEoT ILL 

Po Be HEMMIG 

ANL 

AEC 

o: NEEDED FOR FAST REACTOR CALCULATIONS 

OOPPLER EFFECTo 

!NCLUDING 

Z.14025 1Oo 0 EV 5o 00 KEV 2 CCP M oNc NIKOLAEV FEI 

o: NEUTRON AND CAPTURE WIDTHS WANTED FOR EVALUATION 

OF SELF SHIELDING IN RESOLVED RESONANCE REGIONS 

ANO EVALUATION OF AVERAGE RESONANCE PARAMETERS© 

SELF-INOICATION CAPTURE MEASUREMENTS ARE DESIRED 

FOR P-WAVE RESONANCE OBSERVATION 

0: AVERAGE S AND P WAVE RESONANCE PARAMETERS SHOULD 

BE DERIVED© 

STATISTICAL ANALYSIS OF MEASURED RESONANCE 

PARAMETERS WANTED; 

SEE ALSO GENERAL COMMENTS IN THE INTRODUCTION© 


STATUS 

STATUS 

RPI HOCKENBURY+ - NSE 49 153(1972). PARAMETERS FOR 35 RESONANCES© 

GEL WE IGMANN+ - JNE 26 643(1972). NEW ANALYSIS© 

94 PLUTONIUM 241 NEUTRCN TOTAL CROSS SECTION 

6.52455 1o 00 KEV 1o 00 MEV 1OoOX 2 GER EoGOEL KFK 

692457 1 o 00 MEV 1 5o 0 MEV lOoOX 3 GER EoGOEL KFK 

STATUS 

STATUS 

GEL BOECKHOFF+ - EANOC(E)-150 (1972). WORK IN PROGRESS ©7 TO 700 EVo 

ORL SIMPSON* - IN PROGRESS TC 8 MEVo 

94 PLUTONIUM 241 NEUTRCN ABSCRPTICN CROSS SECTION 

Z1ZSS5 ISoO EV 8o OX J o G;TYROR WIN 


E AND 2Ec 

O: FOR THERMAL REACTORSo 

Z12Q9£ 1.00 KEV 2© 00 KEV 2 0 e 0 X Jo Go TYROR WIN 


E AND 2Eo 



6U132 2 Eo 3 30o 0 KEV 3o0X Bo hUTCHINS GEB 

0: ALPHA ALSO USEFULc 

A: ACCURACY TO 3 PERCENT IN ETAo 

o: IMPROVED PRECISION NEEDED FOR THERMAL REACTORSo 

ALSO WANTED FOR FAST REACTORSo 

6524Z0 1© 00 KEV SoOO MEV 1 Oo OX SWD HoHAEGGBLOM AE 


6S24Z1 200© EV lo 00 MEV GER EoGOEL KFK 

0: ALPHA IS USEFULc 

zs&aai 5©00 KEV 10»0 MEV 

STATUS 

M: 

LoNoUSACHEV 

FROM Oc 5 

PRIORITY 

FROM 0©1 

PRIORITY 

FROM OoS 

PRIORITY 

FEI 

100 KEV ACCURACY 18 PERCENT. 

ACCURACY 18 PERCENTo 

0=8 MEV ACCURACY 30 PERCENT, 


4 o 5 MEV ACCURACY 50 PERCENT, 


ABOVE 4o 5 MEV REQUIREMENTS 2 TIMES WEAKER© 



NEW REQUESTo 

ORL WESTON* - l.SNOC-3 149(1972), WORK IN PROGRESS THERMAL TO 30 KEVc 

SOR CANER+ - IA-127C(1S73). EVALUATION TO 15 MEV 


94 PLUTONIUM 241 TOTAL PHOTON PRODUCTION CROSS SECTION 

652460 120c KEV 20o0X CoGoCAMPBELL WIN 

Q: GAMMA SPECTRUM WANTEDo 



0: FOR STUDY OF ACTIVATION AND HEAT RELEASE IN COREo 


661S5S 1 So 0 MEV loOX Go EcHANSEN LAS 

Q: RATIO TO U-235 FISSION WANTEDc 


662022 1 Oo 0 KEV 1 5o 0 MEV lOoOX P ScKATSURAGI JAE 

O: RESONANCE PARAMETERS ALSO REQUIREDo 

O: FOR FAST REACTORo 


6S1J26 

2 So 3 MV 

30o 0 

KEV 

CoEoTILL 

Bo HUTCHINS 

ANL 

GEB 

Q: RATIO TO U-235 OR PU-239 USEFULo 

A: ACCURACY 3 PERCENT BELOW 10 EV. 10 PERCENT ABOVE 

10 EVo 

692462 

1 OOo EV 

150o 

KEV 

Co Gc CAMPBELL 

WIN 


E AND 2Ec 


692463 

loOO 

KEV 

So 00 

MEV 

lOoOX SWC Ho HAEGGBLOM 

AE 

O: NEEDED FOR FAST REACTOR CALCULATIONSo 

221094 

1o 00 

KEV 

1Oo 0 

MEV 

USA 

Po Bo HEMMIG 

AEC 

0: RATIO WANTED RELATIVE TO U-235o 

232099 

So 00 

KEV 

HoTELLIER 

0: REACTOR CALCULATIONSc 

24201.3 1 o 00 KEV 1 5o 0 MEV Eo GOEL 

254002 SoOO KEV I Oo 0 MEV LoNo USACHEV FEI 

FROM 0 c 5 - 100 KEV ACCURACY 5o0 PERCENT, 

PRIORITY 2 ACCURACY 3o 7 PERCENTc 

FROM Oo 1 - OcB MEV ACCURACY 5o 3 PERCENT, 


FROM 0o8 - 4o5 MEV ACCURACY 10 PERCENT. 





NEW REQUESTo 

-STATUS 

SAC 

KFK 

LRL 

GEL 

ORL 

WIN 

MTR 

BLONS* - NSE 51 130(1973), CATA 1 EV TO 30 KEVo 

KAEPPELER* - NSE 15 124(1973). DATA 10 KEV TO lo2 MEV RELATIVE TO U-235o 

BEHRENS* - MEASUREMENTS PLANNED FCR 1975c 

THEOBALD* - EANDC(E)-150 (19721. IN PROGRESSo 

WESTON* - LSNDC-7 179(1973), IN PROGRESS THERMAL TO 20 KEVo 

JANES - AEfiE-R-6676(1971 I. EVALUATION TO 20 EVo 

SMITH* - IN-14C7 57(19701. EVALUATION TO 50 EVo 

94 PLUTONIUM 241 NEUTRON CAPTURE TO FISSION RATIO (ALPHA) 

6513 21 IcOO KEV 2o 00 MEV lOoOX Bo HUTCH INS 

Po Bo HEMMIG 

GEB 

AEC 

Q: CAPTURE CROSS SECTION EQUALLY USEFULo 


652465 lOOo EV 1 o 00 MEV 20o0X CoGoCAMPBELL WIN 


E AND 2Eo 


Zfl2042 2So 3 MV 1 o OX HoTELLIER SAC 


DISCREPANClESo 

202044 5 00o EV lo 00 MEV 1 5o OX JoYoBARRE CAD 

Q: ABSOLUTE VALUES USEFUL BUT REQUEST CONCERNS MAINLY 

RELATIVE VALUES VERSUS ENERGYo 



94 PLUTONIUM 241 NEUTRON CAPTURE TO FISSION RATIO (ALPHA) (CONTINUED) 

STATUS 

STATUS 

ORL WESTON* - USNDC-7 179(1973), IN PROGRESS THERMAL TO 200 KEVo 

ANL DAVEY - 70HELSINKI 2 1190 REVIEW , Ool To 10 MEVo 

KAP EILAND* - NSE 44 180(1971), PILE SPECTRUMo 

94 PLUTONIUM 241 NEUTRON NEUTRCNS EMITTED PER NEUTRON ABSORPTION (ETA) 

642007 1Oo 0 MV 15o 0 EV 2 UK JoGoTYROR WIN 

0: VALUE RELATIVE TO 25o3 MV ETA WANTEOo 

A: ACCURACY 2 PERCENT TO 1 EV, 6 PERCENT ABOVEo 


652464 2 So 3 MV loOX 2 FR HoTELLIER SAC 

0: FOR THERMAL REACTOR CALCULATIONSo 

EVALUATION MAY SUFFICE IF IT EXPLAINS 

0 I SCREPANCIESo 

94 PLUTONIUM 241 NEUTRCN NEUTRONS EMITTED PER FISSION (NU BAR) 

6S1J30 ' 1 o 00 KEV loOO MEV 4o0X 1 USA Pe Bo HEMMIG AEC 


632466 1o 00 KEV 1 So 0 MEV SoOX 2 GER BoGOEL KFK 

721095 1o 00 MEV lOoO MEV 6oOX 1 USA CoEcTILL ANL 


754013 SoOO KEV 10,0 MEV 1 CCP LoNoUSACHEV FEI 

A: FROM OOS - 100 KEV ACCURACY 1,8 PERCENT, 

PRIORITY 2 ACCURACY 1,2 PERCENT, 

FROM 0,1 - 0,8 MEV ACCURACY 2,6 PERCENT, 

PRIORITY 2 ACCURACY 2,3 PERCENTo 

FROM OoB - 4o 5 MEV ACCURACY 4,0 PERCENT. 


ABOVE 4,5 MEV REQUIREMENTS 2.TIMES WEAKER, 

O: NEED FOR FAST REACTOR CALCULATIONSo 



STATUS 

STATUS 

IAE MANERO* - REA 10 637(1972), REVIEWo 

LRL HOWE* - NCSAC-42 130(1971), IN PROGRESS TO 15 MEVo 

94 PLUTONIUM 241 " NEUTRCN FliiION~FRODUCT~MAS5~YIELD~SPicTRUM 

711604 2 5o 3 MV 1o 0 X 2 CAN Wo Ho WALKER CRC 

Q: YIELD OF XE-135 WANTEDo 

0: FOR CALCULATION OF FISSION PRODUCT ABSORPTION, 

STATUS 

STATUS 

HAR CROUCH - 72 PARIS PAPER 94. THERMAL EVALUATION, 

CRC WALKER - 73 PARIS PAPER 34. THERMAL EVALUATION, 

GEV MEEK* - NECO-12154, THERMAL EVALUATION, 

94 PLUTONIUM 241 NEUTRON RESONANCE PARAMETERS 

632453 3 Eo 0 EV 200o EV lOoOX 2 GER BoGOEL KFK 

Q: NEUTRON WIDTHS NEEOEDo 

Z21140 25,3 MV 4 OOo EV 2 USA CoEoTILL ANL 

A: ACCURACY 5 PERCENT TO 100 EV AND 10 PERCENT ABOVE, 

ACCURACY 20 PERCENT USEFULo 

O: FOR THERMAL AND FAST REACTOR CALCULATIONS, 


Z02S47 2 5,3 MV HoTELLIER SAC 


0ISCREPANCIESO 

Z02046 5,00 KEV He TELL IER SAC 

A: ACCURACY FOR RATIO TO THERMAL CROSS SECTIONo 


0 ISCREPANCIESO 

l l Z l Q i SOOo EV loOO MEV 1 SoOX Jo Yc BARRE CAD 

»: RELATIVE VALUES VERSUS ENERGY OR TO U-238 CAPTUREo 


li.1096 1 e 00 KEV 7,00 MEV 20,0* USA P o Bo HEMMI G AEC 

O: FOR FAST BREEDER CALCULATIONS. CM AND CF 

PRODUCTION, 

FISSION LIST PAGE He 95

95 AMERIC1UM 241 NEUTRON CAPTURE CROSS SECTION (CONTINUED I 

221142 7o OC MEV EoHUTCHINS GEB 

ACCURACY 3 PERCENT TO 100 EV, 10 PERCENT 100 EV TO 

1 KEV. 15-20 PERCENT 1 KEV TO 7 MEVo 

RESONANCE PARAMETERS TO 10-20 PERCENT BELOW 

10 KEVo 

FOR FAST BREEDER CALCULATIONS. CM AND CF 

PRODUCTIONo 

742510 loOO KEV 5o 00 MEV SWD Ho HAEGGBLOM AE 

0: FAST REACTOR CALCULATIONSo 

754014 5o00 KEV 1Oo 0 MEV LoNoUSACHEV FEI 

FROM 0 c 5 

PRIORITY 

FROM Ool 

PRIORITY 

FROM 0o 8 

PRIORITY 

100 KEV ACCURACY 30 PERCENT, 


Oo 8 MEV ACCURACY 30 PERCENT, 

ACCURACY 30 PERCENTc 

4c S MEV ACCURACY SC PERCENT, 





NEW REQUESTc 

-STATUS 

GEL 

RPI 

ORL 

SOR 

MTR 

CRC 

POORTMANS* - NF/A 207 342(1973). DATA 2 EV TO lo3 KEVc 

SANISLO* - LSNCC-11 220(1974), KEV TIME-OF-FLIGhT DATA BEING ANALYZEDo 

WESTONo - (1574), DATA TC 200 KEVo 

CANER* - I A-12 75 ( 1973 ). EVALUATION TO 15 MEVo 

YOUNG* - IN-140 7 63(lS70)o THERMAL VALUE 

DURHAM* - CJP 46 716(157C)o THERMAL VALUE 


742005 1o 00 KE V 5o00 MEV 1 Oo OX SWC Ho HAEGGBLOM AE 



551534 SOOo KEV 

1Oo 0 

MEV 

SoOX 

USA 

Po BohEMMIG 

212100 SOOo EV 

15o 0 

MEV 

SoOX 

FR 

JoYc BARRE 

Q: RELATIVE TO CF-252 NUo 



252031 1 Oo 0 MEV Rc YUMOTO 

HoMATSUNOBU 

PNC 

SAE 

A: ACCURACY REQUIRED 10 TO 20 PERCENTo 

0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF 

TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo 

NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo 


-STATUS 

A NL 

ANL 

ANL 

LRL 

LRL 

STUDIERO - PR 93 1433(1954), THERMAL VALUEo 

BENTLEY* - 55GENEVA 7 261(1955), PILEo 

FIELDS* - NSE 1 62(1556), PILEo 

INGLEYt - AF 3 C 509( 1967). ESTIMATE AT 20 KEV FROM NUCLEAR EXPLOSION (TWEED) DATAo 

INGLEY+ - NF/A 124 13C(1S6S), ESTIMATE FROM FU-242 FISSION YIELDSo 


252025 500c KEV lOoOX RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 

REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF 



NEW REQUESTo 

252030 

2« 00 MEV lOoO MEV lOoOX RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 




NEW REQUESTo 

STATUS- 

-STATUS 

LAS BELL* - PR 158 1127(1967), ESTIMATE AT 10 KEV FROM NUCLEAR EXPLOSION (TWEED! DATAo 

ANL DIAMOND* - JIN 30 2553(1968). THERMAL COLUMN CATA 

JAP NO EXPERIMENTAL DATA IN ENERGY RANGE 2 TO 10 MEVo 



651504 2 So 3 MV 2 CAN 

A: 

0: 

W o Ho WALKER 

CRC 

ACCURACY REQUIRED 200 Bo 

UNKNOWN CROSS SECTION, 

95 AMERICIUM 241 NEUTRON TOTAL CROSS SECTION 

691536 2 So 3 MV 3oOX 2 USA GoToORTON RL 

95 AMERICIUM 241 NEUTRCN ABSORPTICN CROSS SECTION 

681505 25o3 MV SoOX 2 CAN 

O: 

Wo Ho WALKER 

CRC 

WIDE SPREAD OF AVAILABLE VALUE So 

681506 1 o 00 EV 590o EV lOcOX 2 CAN 

Wo Ho WALKER 

CRC 

O: 

CESIRc CONFIRMATION OF RESONANCE INTEGRALo 

Z12106 25o 3 MV SoOX 2 FR HoTELLIER SAC 

95 AMERICIUM 241 NEUTRON CAPTURE CROSS SECTION 

671135 25o 3 MV 1o 00 KEV lOoOX 1 USA 

Fo Jc MC CROSSON SRL 

0: 

o: 

PRODUCTION OF AM-242 AND AM-242 M WANTEDo 

NEEDED FOR PU-22B PROGRAM, AND PRODUCTION OF 

CM — 24 4o 

6Z1136 2 5o 3 MV 1o 00 KEV lOoOX 2 USA 

GoToORTON 

BNW 

o: 

0: 

M: 

PRODUCTION OF AM-242 AND AM-242 M WANTEDo 

NEEDED FOR PU-238 PROGRAM, AND PRODUCTION OF 

CM-244c 

NEW REQUEST, 

68180Z 25o 3 MV SoOX 2 CAN 

Wc He WALKER 

CRC 

o: 

PRODUCTION OF BOTH AM-242 ISOMERS WANTEDo 

681808 1o OC EV 500o EV lOoOX 2 CAN 

WoHoWALKER 

CRC 

O: 

DESIRE CONFIRMATION OF RESONANCE INTEGRAL 

MEASUREMENT OF BAK (AE 23 316)o 

Z121Q8 1 Oo 0 KEV loOO MEV lOoOX 1 GER 

BoGOEL 

KFK 

O: 

FOR BURNUP CALCULATIONSc 

Z121Q9 1 OOo EV 1OOo KEV 20o 0 X 1 UK 

O: 

CoGoCAMPBELL 


WIN 

Z12110 500o EV 1o 00 MEV lOoOX 2 FR 

JoYoBARRE 

CAD 

o: 

o: 

RELATIVE TO U-236 CAPTUREc • 


12iaas 2 5o 3 MV 1 Oo 0 MEV 1 SoOX 2 USA 

BoHUTCHINS 

GEB 

o: 

FOR SPENT FUEL SHI ELD INGo 

Z22116 1 OoOX 1 UK 

o: 

0: 

CoGoCAMPBELL 

AoWHlTTAKER 

WIN 

UKW 

AM-242 ISOMER RATIO WANTEDo 

QUANTITY TO BE AVERAGED OVER A FAST REACTOR AND 

A FISSION SPECTRUMo 

FOR FAST REACTORS AND FUEL REPROCESSINGo 

Z .41122 loOO KEV 2o 00 MEV 20o OX 1 USA 

PcBcHEMMIG 

AEC 

a: 

o: 

M: 

PRODUCTION OF BOTH AM-242 AND AM-242M WANTEDo 

FOR SPENT FUEL SHIELDINGo 

NEW REOUESTc 

242014 25o3 MV 1 Oo 0 KEV 1 OoOX 2 GER 

EoGOEL 

KFK 

o: 

BURN UP CALCULAT IONSc 

Z42015 lo 00 MEV 1 5o 0 MEV lOoOX 2 GER 

BCGOEL 

KFK 

O: 

BURN UP CALCULATIONSo 

Z421Q8 loOO KEV 3o 00 MEV SoOX 2 FR 

Ao M ICHAUDON 

BRC 

o: 


232032 lOoO MV 1 OOo MV 1 JAP 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 

0: ENERGY DEPENDENCE WANTEDo 







95 AMERIC1UM 241 NEUTRON CAPTURE CROSS SECTION (CONTINUED I 

26203.3 2 Co 0 EV 1 Oo 0 MEV lOoOX RoYUMOTO 

hoMATSUNOBU 

PNC 

SAE 

0: PRODUCTION OF AM-242 AND AM-242 M WANTED 

O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF 




BUC 

BUC 

FEI 

KFK 

CCP 

HAR 

ORL 

HAR 

FLEROV+ NF/A 102 443( 1967), DATA Oc 3 TO 6oB MEVo 

VILCOVo - SCF 22 795(1970). DATA AT 7 MEVo 

DOVBENKO+ - INCC(CCP)-9 7(1970). THERMAL. 

HINKELMANN - KFK-1186(1970). EVALUATION TO 10 MEVo 

1VANOVA+ - AE 30 369(1971), CROSS SECTION FOR FAST REACTOR SPECTRUMc 

WILTSHIRE* AERE-R-7363(1973). CROSS SECTION FOR FAST REACTOR SPECTRUMc 

WESTON* - USNOC-7 179(1973). THERMAL TO 20 KEVo IN PROGRESSo 

COATESo (1974). MEASUREMENTS PLANNED. AWAITING SAMPLES? 

93 AMERICIUM 241 NEUTRON FISSION CROSS SECTION 

112X02 SOOo EV ISoO MEV JoY;BARRE 

O: RELATIVE TO U-235 FISSIONo 


232115 1 OOo EV 1OOo KEV UK CoGc CAMPBELL WIN 

o: FOR FAST REACTORSo 

242316 lo 00 KEV 1 5o 0 MEV GER BoGOEL KFK 

o: FAST REACTOR DESIGNo 

242102 loOO KEV ISoO MEV 3o0X FR AoMICHAUDON BRC 

STATUS- 


ORL 

HAR 

CCP 

FEI 

KFK 

WESTON* - LSNDC-7 179(1973). IN PROGRESS THERMAL TO 200 KEVo 

LYNN - MEASUREMENT PLANNEDo 

FOMUSHKIN*- SNP 10 529(1970). 440 KEV TO 3o6 MEVo 

SHPAK+ - INDC < CCP)-8 6(1970), 8 KEV TO 3o3 MEVo 

HINKELMANN - KFK-1186(1970). EVALUATION TC 10 MEVc 

95 AMERICIUM 241 NEUTRON NEUTRCNS EMITTED PER FISSION (NU BAR) 

212104 lOOo KEV lo 00 MEV SoOX 1 GER 

BoGOEL 

KFK 

o: 

FOR FAST REACTOR DESIGNc 

1121 05 SOOo EV 1 4o 0 MEV SoOX 2 FR 

Q: 

o: 

JoYc BARRE 

CAD 

RELATIVE TO CF-252 NUo 


Z42016 25o 3 MV 100. KEV lOoOX 2 GER 

o: 

Eo GOEL 

KFK 

FAST REACTOR DESIGNc 

Z42012 1 o 00 MEV 1 Oo 0 MEV 10.0X 2 GER 

o: 

Eo GOEL 

KFK 

FAST REACTOR DESIGNc 

95 AMERICIUM 241 NEUTRON ABSORPTION RESONANCE INTEGRAL 

1.12132 1 Oo OX 2 FR HoTELLIER SAC 

95 AMERICIUM 242 NEUTRCN TOTAL CROSS SECT ION 

671137 25o3 MV 1 Oo 0 KEV 10.OX 2 USA 

FoJcMC CROSSON SRL 

Q: 

o: 

NEED AM-242 AND AM-242M RESONANCE ENERGIESo 

FOR PU-238 PRODUCTIONO 

95 AMERICIUM 242 NEUTRCN CAPTURE CROSS SECTION 

6S1341 25.3 MV lOoO KEV 2 USA 

Fe Jo MC CROSSON SRL 

o: 

A: 

o: 

M: 

WANTED FOR BOTH 16 HOUR AND 152 YEAR ISOMERSo 

THERMAL VALUE AND RI WANTED. 

REQUIREO ACCURACY - 10 TO 20 PERCENTo 

FOR PU-238 PRODUCTION. 


211663 2 5.3 MV 2 CAN 

WoH.WALKER 

CRC 

o: 

A: 

FOR 16 HOUR ISOMERo 

ACCURACY REQUIRED 500 Bo 

UNKNOWN CROSS SECTIONo 


95 AMERICIUM 242 NEUTRCN CAPTURE CROSS SECTION (CONTINUED) 

121100 2 Eo 3 MV 1 Oo 0 MEV 1 SoOX 2 

USA Eo HUT CHINS GEB 

0: FOR SPENT FUEL SHIELOINGo 

122101 1 Oo 0 MV So 00 KEV lOoOX 2 

FR HoTELLIER SAC 

0: FOR METASTABLE STATE OF AM-242 ( 152 YEARS) o 

O: FOR BURN UP PHYSICSo 

EVALUATION MAY 8E SUFFICIENTo 

132102 5 OOo EV 15o 0 MEV 20o OX 3 FR JoYc BARRE 

FOR METASTABLE STATE OF AM-242 ( 152 YEARS)o 

VALUE RELATIVE TO U-238 CAPTURE CROSS SECTIONo 


252035 25o3 MV 1 Oo 0 MEV RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 

O: WANTED FOR GROUND AND ISOMERIC STATE So 






STATUS 

-STATUS 

CRC HANNA* - PR 81 853(1951)o 

LRL STREET - PR 65 125(1952lo 

LRL BOWMAN* - PR let 1219(1968). RESONANCE PARAMETERS TO 4 EVo 

JUL IHLE+ - JIN 34(6) 2427(1972). PILEo 


6S123S 2=o 3 MV 1 Oo 0 KEV 2 

USA FoJoMC CROSSON SRL 

0: WANTED FOR BOTH 16 HOUR AND 152 YEAR ISOMERSo 

A: REQUIRED ACCURACY - 10 TO 20 PERCENTo 


232100 5 OOo EV ISoO MEV 20o0X 3 

FR JoY,BARRE CAD 

o: FOR METASTABLE STATE OF AM-242 (152 YEARS)o 

VALUE RELATIVE TO U-235 FISSION CROSS SECTIONo 

0: FOR FAST REACTOR CALCULATIONSO 

252034 1 o 00 MEV 6o 00 MEV 1 JAP RoYUMOTO PNC 

HoMATSUNOBU 

SAE 

Q: WANTED FOR GROUND STATE OF AM-242, 






252035 6o 00 MEV 1Oo 0 MEV 

Ro YUMOTO 

HoMATSUNOBU 

PNC 

SAE 

M: 

WANTED FOR GROUND AND ISOMERIC STATESo 

ACCURACY REQUIRED 10 TO 20 PERCENTo 




NEW REQUESTo 

STATUS - 

-STATUS 

LRL BROWNE* - NCSAC-42 135(1971). IN PROGRESS TO 14 MEVo 

LRL PERKINS* - NSE 32 131( 1968). DATA FROM Oo 4 EV TO 4o7 MEVo 

95 AMERICIUM 242 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR)" 

2321133 5 OOo EV 15o 0 MEV 20o0X 3 FR JoYc EARRE 

FOR METASTABLE STATE OF AM-242 (152 YEARS)o 

VALUE RELATIVE TO CF-252 NUo 


95 AMERICIUM 243 NEUTRON ABSCRFTICN CROSS SECTION 

112113 2So 3 MV 

SoOX 2 FR HoTELLIER SAC 

232104 500o EV 

15o 0 MEV 20o0X 2 FR JoY,BARRE CAD 


95 AMcRICIUM 243 NEUTRON CAPTURE CROSS SECTION 

211505 25o3 MV CAN Wo Ho WALKER CRC 

0: DISAGREEMENT BETWEEN INTEGRAL (90 B) AND 

DIFFERENTIAL MEASUREMENTS (180 B)c 

221101 lOoO MEV lOoOX USA BoHUTCHINS GEB 

WANT S TO 10 PERCENT ACCURACY IN THERMAL VALUE 

AND RESONANCE INTEGRALo 

NEEDED FOR LONG TERM REACTIVITY CALCULATIONS AND 

FOR SPENT FUEL SHI ELD 1NGo 

TO DETERMINE CM-244 PRODUCTlONc 



95 AMER ICIUM 243 NEUTRON CAPTURE CROSS SECTION (CONTINUED! 

74-1126 1 c GO KEV 200o KEV Po Bo HEMMIG 

o: FOR SPENT FUEL SHI ELDINGo 


762636 1 Oo 0 MEV 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 

Q: PRODUCTION OF AM-244 AND AM-244 M WANTEOo 






STA TUS- 

ANC 

JUL 

MTR 

BUC 

SIMPSON* - ANCP-1060 (19721. DATA c5 EV TO 1 KEVo 

IHLE* - JIN 34(61 2427(19721. PILEo 

BERRETH+ - IN-14C7 66(1970). RESONANCE PARAMETERS TO 25 EVo 

BOCA+ - NF/A 134 541(1569), DATA 0o3 TO 4 MEVo 


712111 15o 0 MEV JoYo EARRE 

0: RELATIVE TO U-235 FISSIONo 


75233-7 1 Oo 0 MEV 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






STA TUS 

J 

CCP FORMLSHKIN + - YF 5 966(1967), VALUE AT 15 MEVo 

DUB NAD 1 * - JINR-P7-5162(1970), 16 MEVo 

LAS SEEGERc - LA-442C (1970). CATA 49 EV TO 3 MEVo 

95 AMERICIUM 243 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR) 

712.112 500; EV ISoO MEV Jo Yc BARRE 

0: RELATIVE TO CF-2S2 NUc 


95 AMERICIUM 243 NEUTRCN ABSORPTION RESONANCE INTEGRAL 

712.114 1 Oo OX 2 FR HoTELLIER SAC 


25204C 25o 3 MV 1 Oo 0 MEV 2 JAP RoYUMOTO PNC 

HoMATSUNOBU 

SAE 






95 AMERICIUM 244 NEUTRON FISSICN CROSS SECTION 

75263S 2 5o 3 MV 1Oo 0 MEV 2 JAP Ro YUMOTO PNC 

HoMATSUNOBU 

SAE 






STATUS " STATUS 

LAS HUBLETo - HASh-1033 28(1961). THERMALo 

ANL VANDENBOSCH* - JIN 23 187(1962). THERMALo 

96 CURIUM 242 NEUTRCN CAPTURE CROSS SECTION 

6-7113S 2 5o 3 MV 

F o Jo MC 

CROSSON 

o: TARGET HALF-LIFE 163 Do 

o: FOR PU-238 PRODUCTIONO 

712116 ICoO KEV lo 00 MEV lOoOX 

C: FOR CALCULATIONS OF SPONTANEOUS FISSION IN FAST 

REACTORSo 

Z32107 1 Oo 0 MV 5o 00 KEV lOoOX FR HoTELLIER SAC 

•: BURN UP PHYSICSo 

FISSION LIST PAGE Ho 100

95 AMERICIUM 242 NEUTRCN CAPTURE CROSS SECTION (CONTINUED) 

242020 25o3 MV 1OOo KEV lOoOX 

CALCULATIONS OF SPONTANEOUS FISSION 

IN FAST REACTORSc 

2420SI lo 00 MEV 1 So 0 MEV lOoOX 

O: CALCULATIONS OF SPONTANEOUS FISSION 

IN FAST REACTORSo 

152342 2Eo 3 MV 1 Oo 0 MEV 1 JAP Rc YUMOTO PNC 

HoMATSUNOBU 

SAE 

A: ACCURACY REQUIRED 10 TO 20 PEP.CEN T c 





STATUS 

STATUS 

JUL IHLE+ - JIN 34(E) 2427(1972), PILEo 

96 CURIUM 242 NEUTRCN FISSICN CROSS SECTION 

112116 1 OOo KEV 1 So 0 MEV lOoOX 

FOR CALCULATIONS OF SPONTANEOUS FISSION IN FAST 

REACTORSc 

232105 5OOo EV 15o 0 MEV 30o0X JoYcBARRE CAD 

0: VALUE RELATIVE TO U-235 FISSION CROSS SECTIONo 


242012 2 5o3 MV 1 OOo KEV 1 OoOX 

CALCULATIONS OF SPONTANEOUS FISSION 

IN FAST REACTORS AND CALIBRATION 

252041 2 So 3 MV 1Oo0 MEV 1 JAP RoYUMOTO PNC 

HoMATSUNOBU 

SAE 


o: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF 




STATUS 

STATUS 

CRC HANNA+ - FR 61 693(1951). THERMALo 

CCP FOMUSHKIN+ - YF 5 966(1967), 15 MEVo 

JUL IHLE + - JIN 34( 6) 2427(1972), PtLEo 

96 CURIUM 242 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR) 

212112 1OOo KEV 15o 0 MEV SoOX R EcGOEL KFK 

o: FOR CALCULATIONS OF SPONTANEOUS FISSION IN 

FAST REACTORSo 

232106 500o EV 1 So 0 MEV 20o0X 

JoYc BARRE 


0: FOR FAST REACTOR CALCULATICNSo 

24201S 2 5o3 MV 1OOo KEV lOoOX 

O: CALCULATIONS OF SPONTANEOUS FISSION 

IN FAST REACTORSo 

96 CURIUM 242 NEUTRCN RESONANCE PARAMETERS 

6211S2 2So3 MV 1o 00 KEV 20o0X GcTcORTON RL 

o: ELASTIC AND GAMMA WIDTHS WANTEDo 

RADIATIVE CAPTURE AND NEUTRON WIDTHS WANTEDo 

O: FOR PU-238 PROCUCTIONo 


96 CURIUM 243 NEUTRON CAPTURE CROSS SECTION 

211532 2 So 3 MV Wo He WALKER 


0: UNKNOWN CROSS SECTIONo 

252946 10.0 MV lo 00 EV RoYUMOTO 

H.MATSUNOBU 

PNC 

SAE 

O: ENERGY DEPENDENCE WANTED, 

A: ACCURACY REQUIRED 5 TO 10 PERCENT, 






96 CURIUM 243 NEUTRON CAPTURE CROSS SECTION (CONTINUED) 

1SZ0A3 2 Oo 0 EV lOoO MEV Po YUMOTO 

hoMATSUNOBU 

PNC 

SAE 

A." ACCURACY REQUIRED 10 TO 20 PERCENTo 





-STATUS 

JUL IHLE* - JIN 34(E) 2427(1972). PILEo 

JAP o(1975), NO EXPERIMENTAL DATA ABOVE 26 EVo 

96 CURIUM 243 NEUTRON FISSICN CROSS SECTION 

2S20A2 1 Oo 0 M V 1o 00 EV lOoOX 

Ro YUMOTO 

HoMATSUNOBU 

PNC 

SAE 






Z52DA4 

2 Oo 0 E V 

1 OOo 

lOoOX 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 





2S20A5 

3o 00 

MEV 

1Oo 0 

MEV 

RcYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






STATUS- 

JUL IHLE* - JIN 34(C) 2427(1972), PILEo 

LRL BROWNE* - NCSAC-42 135(1971), MEASUREMENT THERMAL TO 

LAS FULLWOOD* - LA-4420 (1970), CATA Ooll TO 2o9 MEVo 

LRL HULET* - PR 107 1294(1957). THERMALo 

JAP o(1975) , NO EXPERIMENTAL DATA FROM 26 EV TC 106KEV 

JAP o(1975) , NC EXPERIMENTAL DATA ABOVE 3 MEV o 


62X1*2 1 Oo 0 KEV 1Oo 0 MEV BohUTCHINS GEB 

A: ACCURACY OF 5 TO 10 PERCENT IN Rio 

0: FOR SPENT FUEL SHIELDINGo 

TO EVALUATE CF PRODUCTIONo 


I321QS 5o 00 KEV lOoOX FR HoTELLIER 

O: BURN UP PHYSIC So 

Z520AS SOOo EV 1 Oo 0 MEV 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 

A: ACCURACY REQUIRED 10 TO 20 PERCENTc 





STATUS 

LAS MOORE* - PR/C 3 1656(1971), DATA 20 EV TO 10 KEVo 

-STATUS 

96 CURIUM 244 NEUTRON FISSION CROSS SECTION 

222X0 S SOOo EV ISoO MEV JoYo EARRE CAD 

O: VALUE RELATIVE TO U-235 FISSION CROSS SECT I ONo 


Z52fl»fl 1 o 00 KEV lOoO KEV RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 




NEW REQUESTc 

-STATUS 

LAS MOORE* - PF/C 3 1656(1971). DATA 20EV TO 3 MEVo 

SRL BENJAMIN* - NSE 47 203(1972). THERMAL CROSS SECTION AND RESONANCE INTEGRAL RELATIVE TO U-235 

FISSION LIST PACE lie 102

96 CURIUM 244 NEUTRONS EMITTED PER FISSION (NU BAR) 

222110 5 COc EV 15o0 MEV 20o OX JoYoBARRE 



96 CURIUM 245 TOTAL CROSS SECTION 

621144 25c3 MV lOoO KEV Fc Jo MC CROSSON SRL 

0: SHAPE OF THERMAL CROSS SECTION ESPECIALLY 

IMPORTANTo 

A: NEED 10 PERCENT IN RESONANCE INTEGRALo 

0: TO EVALUATE CF PRODUCTIONo 


96 CURIUM 245 NEUTRON CAPTURE CROSS SECTION 

6S12AS lOoO KEV 1 OoOX Fo Jc MC CROSSON SRL 

SHAPE OF THERMAL CROSS SECTION ESPECIALLY 

IMPORTANTo 

RESONANCE STRUCTURE NEEDEDo 

NEED 10 PERCENT IN RESONANCE INTEGRALo 

NEED INTEGRAL ALPHA TO 10 PERCENTo 

TO EVALUATE CF PROOUCTIONo 


222052 1 OoO MV loOO EV lOoOX RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






252054 

6 Oo 0 E V 1 Oo 0 MEV 20o 0 X RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 




NEW REOUESTc 

-STATUS 

ANL 

ANL 

ANL 

ORL 

J AP 

STEVENS* - PR 94 974(1954). PILEo 

BENTLEY+ - 55 GENEVA 7 261(1955), PILEo 

JAFFEYo - NSE 1 204(1956), THERMALo 

HALPERIN* - ORNL-4437 20(1969), THERMALo 

o(1975), NO EXPERIMENTAL CATA ABCVE 60 EVo 

96 CURIUM 245 NEUTRCN FISSION CROSS SECTION 

621145 

lOoO 

KEV 

Fo Jo MC CROSSON SRL 

o: SHAPE OF THERMAL CROSS SECTION ESPECIALLY 

IMPORTANTo 


NEED INTEGRAL ALPHA TO 10 PERCENTo 



252050 lOoO MV 

1 o 00 EV 

JAP 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






ZS2051 60o0 EV 

1 Oo 0 KEV 

JAP 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






Z52052 3o 00 MEV lOoO MEV JAP RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 

A: ACCURACY REQUIRED 10 TO 20 PERCENT® 


TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUEL* 



F'ISSION LIST PAGE I lo 10 3

96 CURIUM 245 NEUTRON FISSICN CROSS SECTION (CONTINUED) 

CCP FORMLSHKIN* - IF 17 24(1573 >c 

SRL BENJAMIN+ - NSE 4 7 203(1972), THERMAL CROSS SECTION AND RESONANCE INTEGRAL RELATIVE TO U-235 

LAS MOORE+ - PR/C 3 1656(1571), CATA 2C EV TO 3 MEVc 

SRL THOMPSON* - JIN 33 1553(1971), PILEo 

SRL RUSCHEo - AOS 14 344(1571). THERMALo 

ORL HALPERIN* - ORNL-4581 (1970), THERMALo 

SRL SMITH* 68WASH PAPER H12 (1968). THERMAL AVERAGEc 

LRL HULET+ PR 107 1254(1957), THERMALo 

ANL JAFFEYO - NSE 1 204(1956). THERMALc 

LRL BROWNE* - NCSAC-42 135(1971), WORK PLANNECo 

96 CURIUM 246 NEUTRCN TOTAL CROSS SECTION 

b l l l i t 25o 3 MV lOcO KEV lOoOX FoJo MC CROSSON SRL 

a: SHAPE OF THERMAL CROSS SECTION ESPECIALLY 

IMPORTANT,: 

RESONANCE STRUCTURE OESIREDo 

A: ACCURACY 10 PERCENT IN RESONANCE INTEGRALo 

M! SUBSTANTIAL MODIFICATIONSo 

96 CUR IUM 246 NEUTRCN CAPTURE CROSS SECTION 

6S1350 25o3 MV lOcO KEV lOoOX A Fo Jo MC CROSSON SRL 

Q: RESONANCE STRUCTURE DESIREDo 

A: NEED ACCURACY 10 PERCENT IN RESONANCE INTEGRALo 

O: TO EVALUATE CF PRODUCTION 

752055 1 Oo 0 MV 5o 00 EV Rc YUMOTO 

HoMATSUNOBU 

PNC 

SAE 

Q: ENERGY DEPENDENCE WANTEDo 





75205S 

4 OOo EV 1 Oo 0 MEV RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 




NEW REQUESTo 

-STATUS 

LAS 

ORL 

SRL 

ANL 

JAP 

MOORE* - PR/C 3 1656(1971). DATA 80 EV TO 400 EVo 

HALPERIN* - ORNL-4437 20(1969). THERMALo 

FOLGER* - 68WASH 1279, THERMALo 

STEVENS* - PR 54 974(1954). PILEo 

o(1975), NC EXPERIMENTAL DATA ABCVE 400 EVo 

96 CURIUM 246 NEUTRGN FISSICN CROSS SECTION 

75.2055 

5c 00 

EV 

20c OX 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






752055 1 o 00 KEV 

1 Oo 0 KEV 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 




NEW REQUESTc 

752057 3o 00 MEV 1Oo 0 MEV 20oGX RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 




NEW REQUESTo 

STATUS 

-STATUS 

SRL THOMPSON* - JIN 33 1553(1971), PILEo 

LAS MOORE* - PR/C 3 1656(1971), DATA 20 EV TO 3 MEVo 

SRL BENJAMIN* - NSE 47 203(1972), THERMAL CROSS SECTION AND RESONANCE INTEGRAL RELATIVE TO U-235 

CCP 

F0MUSHKIN*_YF_12_24

96 CURIUM 247 NEUTRCN TOTAL CROSS SECTION 

6.2114.7 2 5o3 MV 1 Oo 0 KEV FcJc MC CROSSON SRL 


IMPORTANT; 


O: TO EVALUATE CF PRODUCTIONo 


96 CURIUM 247 CAPTURE CROSS SECTION 

6211 SS 25o3 MV 1 Co 0 KEV USA Fc J;MC CROSSON SRL 

O: SHAPE OF THERMAL CROSS SECTION ESPECIALLY 

IMPORTANT; 

A: NEED 5 TO 10 PERCENT IN RESONANCE INTEGRAL AND 

THERMAL VALUEo 

O: NEEDED TO EVALUATE CF PRODUCTIONo 

M: SUBSTANTIAL MODIFICATIONSC 

252063 2 So 3 MV 1 Oo 0 MEV 20o0X 1 JAP R, YUMOTO PNC 

HoMATSUNOBU 

SAE 

STATUS 

JAP o < 1975). NC EXPERIMENTAL CATA IN ENERGY RANGE THERMAL TO 10 MEVc 




M: NEW REQUEST,-. 

96 CURIUM 247 NEUTRON FISSION CROSS SECTION 

621156 

1 Oo 0 KEV 

Fc Jc MC CROSSON SRL 

o: SHAPE OF THERMAL CROSS SECTION ESPECIALLY 

IMPORTANTc 

A: NEED 5 TO 10 PERCENT IN THERMAL VALUE AND 

RESONANCE INTEGRAL; 


252060 2So 3 MV 

20o 0 

EV 

RcYUMOTO 

HoMATSUNOBU 

PNC 

SAE 


A: ACCURACY REQUIRED 5 TO 10 PERCENT, 





252061 6 Oo 0 E V 

lOoO 

KEV 

RcYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






252062 3o 00 MEV lOoO MEV 

Ro YUMOTO 

HoMATSUNOBU 

PNC 

SAE 



TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELc 



STATUS- 

CCP 

SRL 

LAS 

SRL 

SRL 

LRL 

ORL 

ANL 

ANL 

FOfiMLSHKI N* - YF 17 24(1972)o 

BENJAMIN* - NSE 47 203(1972). THERMAL CROSS SECTION AND RESONANCE INTEGRAL RELATIVE TO U-235 

MOORE* - Pfi/C 3 1656(1571). DATA 20 EV TO 2 MEVc 

THOMPSON* - JIN 33 1553(1971), PILE; 

RUSCHEo - ANS 14 344(1571). THERMALo 

BROWNE* - NCSAC-42 135(1571), WCRK FLANNECo 

HALPERIN* - ORNL-4581 37(1970). THERMALo 

DIAMOND* - JIN 30 2553(1968). THERMALo 

SMITH* - 6EWASH PAPER HI 2, FILEo 


252562 25o3 MV 1Oo 0 MEV 1 JAP Rc YUMOTO PNC 

HoMATSUNOBU 

SAE 

A: ACCURACY REQUIRED 1C TO 20 PERCENTo 





STATUS 

STATUS 

ORL HALPERIN* - ORNL-3832 1 (1965), THERMALo 

LAS MOORE* - PF/C 3 1656(1971). DATA 25 TO 100 KEVo 

ORL ORUSCHEL* - ORNL-4891 23(1573), THERMALo 


97 BERKELIUM 249 NEUTRON CAPTURE CROSS SECTION 

631-254 LOCO KEV FoJoMC CROSSON SRL 


IMPORTANTo 

A: 10 PERCENT THERMAL AND RESONANCE INTEGRALo 

O: FOR CF PRODUCTIONO 


252624 2 So 3 MV 1 Oo 0 MEV 20o0X 1 JAP RoYUMOTO PNC 

HoMATSUNOBU 

SAE 





STATUS 

STATUS 

ANL MAGNUSSON* PR 9( 1576(1954), PILEo 

SRL FOLGER+ - 68WASH 1279, THERMALo 

97 BERKELIUM 249 NEUTRCN FISSICN CROSS SECTION 

752672 

2 5o 3 MV 

200o 

2 0 o 0 X 

Ro YUMOTO 

HoMATSUNOBU 

PNC 

SAE 




NEW REQUESTc 

752672 

5o 00 

MEV 

1Oo 0 

MEV 

20 oO X 

Rc YUMOTO 

HoMATSUNOBU 

PNC 

SAE 




NEW REQUESTc 

KUR VOROTNIKOV* - NF/A ISO 56(1970), DATA 0o6 TO 4oC MEVo 

SRL RUSCHEo - ANS 14 344(1571), THERMALo 

CCP FORMUSHKIN+ - YF 14 73( 1971 >. DATA lo 5 TO 15 MEVo 

LRL BROWNE* - NCSAC-42 135(1971), MEASUREMENT FLANNEDo 

97 BERKELIUM 250 NEUTRCN CAPTURE CROSS SECTION 

252626 2So3 MV lOoO MEV 20o0X 2 JAP RcYUMOTO PNC 

HoMATSUNOBU 

SAE 





STATUS 

STATUS 

JAP o(1975), NC EXPERIMENTAL DATA IN THE ENERGY RANGE FROM THERMAL TO 10 MEVo 

97 BERKEL IUM 250 NEUTRON FISSICN CROSS SECTION 

252525 25o3 MV 1Oo 0 MEV 20 o OX 2 JAP RoYUMOTO PNC 

HoMATSUNOBU 

SAE 





STATUS 

STATUS 

ANL DIAMOND* - JIN 30 2553(1968), THERMALo 

98 CALIFORNIUM 249 NEUTRCN CAPTURE CROSS SECTION 

252522 lOoO MEV RcYUMOTO 

HoMATSUNOBU 

PNC 

SAE 

A: 

o: 

ACCURACY REQUIRED 10 TO 20 PERCENTo 




NEW REQUESTo 

STATUS 

BRK HARVEY* - PR «S 581(1954), FILEo 

ORL HALPERIN* - 0RNL-47Q6 4711971 I. THERMALo 

98 CALIFORNIUM 2S0 NEUTRON TOTAL CROSS SECTION 

621132 25o3 MV 1Oo 0 KEV 20o'0X USA FoJoMC CROSSON SRL 

BS=s9BSBasaa*Bsaaae 

j: RESONANCE ENERGIES DESIREDo 

A: NEED 20 PERCENT ACCURACY IN RESONANCE INTEGRALo 

O: TO EVALUATE CF PRODUCTIONo 


9 8 CAL IFOSMIUM 2EC CAPTURE CROSS SECTION 

651551 2So 3 MV lOoO KEV ICoOX A Fo Jc MC CROSSON SRL 


0: TO EVALUATE CF PRODUCTION 

252025 2 So 3 MV I Oo 0 MEV 1 JAP RoYUMOTO PNC 

HoMATSUNOBU 

SAE 






STATUS 

STATUS 

ANL MAGNUSSON+ - PR 56 1576(19541. PILEo 

SRL F 0LGER+ - 6 SWA SH 1279, THERMAL: 

ORL HALPERIN+ - 0RNL-4706 47(1971), THERMALo 

98 CALIFORNIUM 2EC NEUTRON FISSICN CROSS SECTION 

621153 1 Oo 0 KEV A Fo Jc MC CROSSON SRL 



252028 2 5o 3 MV 1Oo C MEV 20oCX 2 JAP RoYUMOTO PNC 

HoMATSUNOBU 

SAE 



NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKc 

M! NEW REQUESTo 

STATUS 

ST AT US 

JAP o(19 75). NC EXPERIMENTAL CATA IN THE ENERGY RANGE FROM THERMAL TO 10 MEVo 

98 CALIFORNIUM 251 NEUTRCN CAPTURE CROSS SECTION 

621154 1Oo 0 KEV lOcOX A Fc Jc MC CROSSON SRL 



752081 2503 MV 1Oo 0 MEV 1 JAP RoYUMOTO PNC 

HoMATSUNOBU 

SAE 






STA TUS 

STATUS 

ANL MAGNLSSON+ - Ffi 56 1576(1554). PILEo 

SRL FOLGER+ - 68WASH 1279. THERMAL VALUEc 

ORL HALP ERIN + - 0RNL-47D6 47(1571 ). THERMALo 

98 CALIFORNIUM 2S1 NEUTRCN FISSICN CROSS SECTION 

241132 

1Oo 0 

KEV 

1 OoOX Fo Jc MC CROSSON SP.L 

Q: THERMAL CROSS SECTION SHAPE ESPECIALLY IMPOR TANTc 

A: NEED 10 PERCENT ACCURACY IN RESONANCE INTEGRALo 



752060 

1 Oo 0 MEV 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






ANL METTA+ - JIN 27 33(1965). THERMAL VALUEo 

SRL SMITH* - 68WASH .PAPER HI 2. PILEo 

SRL RUSCHEo - ANS 14 344(1571), THERMAL VALUEo 

LRL RAC-AINlo - PR/C 5 399( 1974)o THERMAL VALUEo 

98 CALIFORNIUM 252 SPONTANEOUS NEUTRONS EMITTED PER FISSION (NU BAR) 

651555 Oo 25X USA PoBohEMMIG 

RoSoCASWELL 

AEC 

NBS 


o: FOR USE AS STANDARDo 


212115 PoRIBON SAC 

o: DISCREPANCY BETWEEN DIFFERENTIAL AND MAXWELL 

SPECTRUM EXPERIMENTS HAVE TO BE RESOLVED 

FOR 2200M/S DATAo 


98 CALIFORNIUM 252 SPONTANEOUS NEUTRONS EM ITT EO PER FISSION (NU BAR) (CONTINUED) 

114232 MoNoNIKOLAEV FEI 

ACCURACY NOT WORSE THAN 0„3 PERCENTo 

MUST BE GUARANTEED BY AGREEMENT WITHIN OoS PERCENT 

OF AT LEAST FOUR EXPERIMENTS CARRIED OUT BY NOT 

LESS THAN TWO DIFFERENT METHOD So 

SEE GENERAL COMMENTS IN THE IN TROOUC TI ONo 


RECONCILE THIS STANDARD WITH MACROSCOPIC 

EXPERIMENTS; ' 


241130 0o25X 

A RoEHRLICH KAP 

A: ACCURACY 1 PERCENT OR BETTER USEFULo 

o: FOR USE AS A STANDARDo 


-STATUS 

AUA 

I AE 

NPL 

ANL 

MHG 

I AE 

BOLDEMAN* - INCC(SEC)-35 (1973), FINAL VALUEo 

MANERO* - REA 10 637(1972). REVIEWo 

AXTON - BELIEVES DISCREPANCIES DUE TC DIFFERENT MEASUREMENT TECHNIQUES NO LONGER EXISTo 

SMITHo (1974). STUDYING NUEAR VSo ETA CISCREPANCYo 

o(1974). WORK BEING PLANNECo 

LEMMELo 7SWASH . REVIEW AND LEAST-SQUARES ANALYSIS WITH THERMAL PROPERTIES OF OTHER FISSILE NUCLEIo 

98 CALIFORNIUM 252 SPONTANEOUS ENERGY SPECTRUM OF FISSION NEUTRONS 

112122 2oOX 

Q: SECONDARY NEUTRON ENERGIES TO 14 MEV REQUIREDo 

O: STANDARDO 

Z21105 SoOX USA RoSoCASWELL NBS 

0: FOR USE AS A STANDARDo 

Z22117 Bo ROSE HAR 

ACCURACY FOR MEAN SPECTRUM ENERGYo 

10 PERCENT ACCURACY WANTED FOR THE NUMBER OF 

NEUTRONS ABOVE 5 MEV AND BELOW o 25 MEVo 

STANDARDo 

Z41131 USA RoEHRLICH 

0: 

o: MEAN SPECTRUM ENERGY TO 1 

FOR USE AS A STANDARDo 


STATUS- 

-STATUS 

BET 

GEL 

GEL 

CCP 

LRL 

HAR 

LAS 

AUA 

GREENt - NSE 50 257(1973). DATA OoS TO 13 MEVo 

KNITTER* - AKE 22 84(1973). DATA Oo15 TO 15 MEVo 

KNITTER* - NEANDC(E)-161 208(1974) . PRELIMINARY DATA AVA ILABLEc 

ALEK SANDRO VA* - AE 36 282(1974)o 

BROWNE* - FR/C 10 2545(1974), HAUSER-FESHEACH CALCULATION OF FISSION NEUTRON SPECTRUMo 

FERGUSON* CATA BEING ANALYZED© 

AUCHAMPAUGH* MEASUREMENTS CCMPLETEDo 

BOLDEMAN* MEASUREMENTS PLANNEDo 

98 CALIFORNIUM 252 NEUTPCN CAPTURE CROSS SECTION 

6ZH5E 1 Oo 0 KEV lOoOX Fo Jo MC CROSSON SRL 



152034 2 5o 3 MV 1 Oo 0 MEV JAP 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






STA TUS- 

BRK 

HARVEY* - PR 95 581(1954). FILEo 

-STATUS 

ANL 

SRL 

ORL 

ORL 

KFK 

MAGNUSSON* - PR 96 1576(1954), PILEo 

FOLGER* - 68WASH 1279. THERMAL VALUEo 

HALPERIN* - NSE 37 228(1969), THERMAL VALUEo 

BEMISo - NSE 41 146(1970), PILEo 

EBERLE* - KFK-1338 (1971), FILEo 


98 CALIFORNIUM 252 NEUTRCN FISSICN CROSS SECTION 

252062 2So 3 MV 

20o 0 EV lOoOX 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 

O: ENERGY DEPENDENCE WANTEDo 





252062 So 00 MEV 

1Oo 0 MEV 20o0X 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 




NEW REOUESTc 

STATUS 

ORL BEMISo - NSE 41 146(1570), FILEo 

LAS MOORE* - PR/C 4 273(1971), NUCLEAR EXPLOSION, 20 EV TO 5 MEVc 

ORL HALPERIN+ - 0RNL-4706 53(1971). THERMAL VALUEo 

JAP o(19751, NC DATA IN THE ENERGY RANGE 5 TO 10 MEVo 

98 CALIFORNIUM 253 NEUTRON CAPTURE CROSS SECTION 

252065 2 5o 3 MV lOoO MEV 2 JAF RCYUMOTO PNC 

HoMATSUNOBU 

SAE 






STATUS 

STATUS 

ORL BEMISt - NSE 41 146(1570), FILEo 

CCP ANUFRIEV+ - AE 32 493(1972), PILEo ESTIMATED VALUE 

98 CALIFORNIUM 253 NEUTRON FISSICN CROSS SECTION 

252585 2So3 MV lOoO MEV 

RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 






STATUS 

-STATUS 

ORL BEMISt - NSE 41 146(1970), FILEo 

SRL RUSCHEo - ANS 14 344(1971), THERMAL VALUEo 

LRL WILD* - JIN 35(4) 1063(1973). THERMALo 

98 CALIFORNIUM 254 NEUTRON CAPTURE CROSS SECTION 

252-088 25o3 MV 1 Oo 0 MEV 20o0X 2 JAP RoYUMOTO PNC 

HoMATSUNOBU 

SAE 




M! NEW REQUEST, 

STATUS 

STATUS 

BRK HARVEYt - PR 95 581(1954), FILEo UPPER LIMITo 

98 CALIFORNIUM 254 NEUTRCN FISSICN CROSS SECTION 

252063 25o3 WV lOoO MEV RoYUMOTO 

HoMATSUNOBU 

PNC 

SAE 





STATUS 

JAP o( 1975) , NC EXPERIMENTAL CATA IN THE ENERGY RANGE FROM THERMAL TO 10 MEVo 

99 ETNSTEINIUM~253 NEUTRON FISSION CROSS SECTION 

241-125 MV lOoO KEV lOoOX USA Fo Jo MC CROSSON 

SRL 

M: NEW RtUUESTc 


FISSION PRODUCTS NEUTRCN INELASTIC CROSS SECTION 

754022 800= KEV So 00 MEV CCF LoNcUSACHEV FEI 

A: FROM 0 o 8 - 1=4 MEV ACCURACY 13 PERCENT, 


FROM 1o 4 - 2o 5 MEV ACCURACY 15 PERCENT, 

PRIORITY 2 ACCURACY IS PERCENTo 

FROM 2c 5 - SoO MEV ACCURACY 30 PERCENT. 


0: NEED FOR FAST REACTOR CALCULATIONo 



FISSION PRODUCTS AESORPTION CROSS SECTION 

6SZdlt 2 So 3 MV SoOX 2 UK JoGcTYROR WIN 

o: FOR THERMAL REACTORS; 

INTEGRAL REQUIREMENT FOR TOTAL FISSION PRODUCT 

POISONING IN IRRADIATED FUELo 

STATUS 

STATUS 

WIN oINTEGRAL EXPERIMENT IN HECTOR PLANNED FOP APRIL 1975 

FISSION PRODUCTS NEUTRCN CAPTURE CROSS SECTION 

655565 

25o 3 

MV 

1 OOo 

JcL:SYMONOS 

AUA 

O: RESONANCE PARAMETERS ALSO REQUIREDo 

S, P AND D WAVE STRENGTH FUNCTIONS NEEDEDo 

O: DESIRED FOR THEORETICAL PREDICTIONS OF CROSS 

SECTIONS FOR MASSES 8O-I6O0 

714Q36 

1 OOo EV 

20 o OX 

MoNoNIKOLAEV 

FEI 

AVERAGE CAPTURE CROSS SECTION FOR LUMPED FISSION 

PRODUCTS. STABLE. LONG-LIVED AND EQUILIBRIUM 

FISSION PRODUCTS 

DATA FOR FISSION PRODUCTS OF u-235. U-238. 

PU-239 AND PU-24C ARE OF GREAT INTERESTo 

SEE GENERAL COMMENTS IN THE I NTRODUCTI ONo 

15451.5 5o 00 KEV 1 Oo 0 MEV CCP 

Lc N 3 USACHEV 

FEI 

FROM Oo 5 - IOC' KEV ACCURACY 8 PERCENT, 


FROM Oo1 - Oc 8 MEV ACCURACY 15 PERCENT, 


FROM O08 - 4o 5 MEV ACCURACY 48 PERCENT, 





NEW REQUESTc 

FISSION PRODUCTS ABSORPTION RESONANCE INTEGRAL 

652495 Oo 55 EV 2o 00 MEV 1 Oc 0 X J0G0TYROR WIN 

STATUS 

WIN cINTEGRAL EXPERIMENT IN HECTOR PLANNED FCR APRIL 1975 


INTEGRAL REQUIREMENT FOR TOTAL FISSION PRODUCT 

POISONING IN IRRADIATED FUELo 

STEEL NEUTRON CAPTURE CROSS SECTION 

7.14C 35 EV 8OC0 KEV CCP McNo NIKOLAEV FEI 

Q: RATIOS WANTED RELATIVE TO U-235 FISSION, B-10. 

L 1-6, HE— 3 AND H-l STANDARDSo 

A: 10 PERCENT BELOW, 20 PERCENT ABOVE 100 KEV WANTEDo 

O: SEE GENERAL COMMENTS IN THE I NTRODUC TI ONo 

ANALYSIS OF FAST CRITICAL ASSEMBLIES INDICATES 

THAT THE CAPTURE CROSS SECTION OF STAINLESS 

STEEL IS MUCH GREATER THAN CALCULATED FROM 

MICROSCOPIC DATAo 

FIRST PRIORITY BECAUSE IT IS DIFFICULT TO EVALUATE 

STEEL CAPTURE CROSS SECTION TO REQUESTED 

ACCURACY FROM MACROSCOPIC EXPERIMENTS ONLYo 


Z54015 So 00 KEV 1 Oo 0 MEV LoNcUSACHEV FEI 

FROM Oo 5 100 KEV ACCURACY 11 PERCENT, 

PRIORITY ACCURACY 11 PERCENTo 

FROM Oo1 O08 MEV ACCURACY 15 PERCENT. 

PRIORITY ACCURACY IS PERCENTo 

FROM O08 4o 5 MEV ACCURACY 20 PERCENT. 

PRIORITY ACCURACY 20 PERCENTo 

ABOVE 4o 5 MEV REQUIREMENTS 2 TIMES WEAKER, 



NEW REQUESTo 

FISSION LIST PACE IIolll

III. i 

III. Fusion Reactor Development 

III.A. 

Introduction 

This is the second publication by the Agency of an 

international nuclear data request list for fusion research 

and reactor development. The previous publication was 

report INDC(NDS)-57 issued in December 1973. 

The present list contains 329 data requests from 

five Member States - France, the Federal Republic of 

Germany, the Soviet Union, the United Kingdom and the 

United States. Since the previous publication the 

requests from the United States have been revised extensively, 

and those from the United Kingdom have been 

qualified by new prefacing remarks concerning priorities 

in their fusion programme. 

Since the data request list for fusion is being 

produced for the first time as part of WRENDA, no lists 

of satisfied and withdrawn requests have been produced. 

Although many of the comments in the introduction 

to the previous list remain valid, the nev; requests seem 

to be based on improved conceptual designs and sensitivity 

studies. It should be noted that some requestors specifically 

ask for evaluations of existing data rather than for new 

measurements.

III.ii 

III.B. 

Supplementary Information from Contributors 

1. France: 

In a letter appended to the data requests received 

from France in 1973i R. Joly cautions that the requests 

should be considered with prudence because without a 

model which permits determination of the consequences 

of uncertainties in nuclear data on the performance of 

a fusion reactor, data needs cannot be established by 

rigorous means. 

2. The United Kingdom: 

In a letter appended to the data requests received 

from the UK in 1973, B. Rose states that the requests are 

for information and that in many cases it is not known 

whether existing data might satisfy certain requests. 

This implies that the requests may be either for measurement 

or for evaluation and that it has not yet proved 

possible to identify each request as being for one or 

the other. The priority designations are based on the 

Agency-developed Priority Criteria of Section III.C. 

The following addendum was communicated to the Agency 

by C.A. Uttley in April 1975 on behalf of the United 

Kingdom Nuclear Data. Committee's Subcommittee for Fusion: 

At present the requests from the UK should still not 

be interpreted as requests for measurements. Initial 

emphasis will be placed on stainless steel as the main 

structural material. The relevant cross sections of the 

components - Fe, Cr and Ni - will be evaluated as a first 

step in defining further data requirements.

Ill.iii 

Over the next six months data requirements for interpretation 

of integral experiments on LiP 

systems are expected to become 

apparent. Immediate data requirements are for inelastic .excitation 

19 

cross sections to the first few excited states of F for incident 

neutron energies of less than 1 MeV to 15 MeV with an accuracy of 

10 to Yjfo and for partial excitation cross sections for different 

modes of ^Li (n,n'a t) to interpret tritium production. A review 

19 

of existing data for inelastic cross sections of F and theoretical 

calculations for ^Li (n, n'a t) are in progress. 

3. The Federal Republic of Germany: 

The following comments regarding the data requests from Germany 

were communicated to the Agency in 1973 by S. Cierjacks: 

It has been shown 3 that in principle a large number of fusion 

reactions can be considered for energy production in a thermonuclear 

reactor. The three most important reactions are the 

following: 

D + T 

D + 3 He 

2D + 2D 

4 He (3.52 MeV) + n (14.O6 MeV) 

^He (3.67 MeV) + p (14.67 MeV) 

T (1.01 MeV) + p (3.03 MeV) 

3 He (0.82 MeV) + n (2.45 MeV) 

Among these the D + "^He-reaction is - from a theoretical point 

of view - the most, interesting process, since both reaction products 

are stable charged particles. Their energy should thus be easily 

utilized, and there might even be a possibility for direct conversion 

of the kinetic energy to electric power. However, 3 He is a very 

scarce component in the natural isotopic composition of helium, and 

consideration of net power yields attainable with the above reactions 

shows that this quantity for the D + T-process exceeds the yield for 

the D + 3 He- and the D + D-rea,ction by two and three orders of magnitude, 

respectively. Therefore, from the present stage of knowledge, 

the first prototype reactor will be most probably a DT-reactor. 

3 V.S. Crocker, S. Blow and C.J.H. Watson, Nuclear Data for Reactors, 

(Proc. Conf., Helsinki, 1970), IAEA, Vienna, 1970, Vol. I, p. 67.

III.iv 

Accepting this point of view, it is apparent that a large 

number of neutron data are necessary. In general various data 

for a large number of promising materials are required from 

thermal energies up to 15 MeV. A complete list of presently 

4 

interesting materials and reactions has been given elsewhere. 

While for most of the elements under consideration sufficiently 

accurate data are available from thermal values up to 

MeV, 

there is a considerable lack of experimental information in the 

energy range from 1 - 15 MeV. 

An inspection of the lists of 

materials which might be used in thermonuclear reactors shows 

that the body of nuclear data 

needed for fusion purposes will 

presumably exceed even the data requirements for the development 

of fission reactors. 

Despite the tremendous extent of 

overall data heeds, the present German request list contains only 

data requirements for five of the most important elements: Li, 

Be, F, Nb, Mo. 

The primary criteria leading to this selection 

arise from priority considerations elaborated in the national 

Memorandum on Fusion Reactor Technology. Major effort in the 

near future will be devoted to tests of computer codes and the 

reliability of microscopic neutron data. 

This can be achieved 

by comparison of experimentally determined and calculated results 

for the characteristic physical parameters (Tritium-breeding 

ratio, space-dependent neutron ajid power distribution etc. ) of 

simple test blankets without any structural material. Our 

understanding of the present request list is, that only the needs 

for the next few years' programme are included. As thermonuclear 

research proceeds, new requests will subsequently be added in the 

coming years. 

The present compilation is a combined list of the three Research 

Centers, Kernforschungszentrum Karlsruhe, Kernforschungsanlage 

Juelich and Max-Planck Institut fuer Plasmaphysik, Garching, which 

are the main laboratories involved in the national fusion reactor 

technology programme. Priority assignments are due to the criteria 

developed previously by the Agency and the International Fusion 

Research Council. Status information has been elaborated by S.Cierjacks 

and R. Meyer, Kernforschungszentrum Karlsruhe, as of June 1972. 

4 M. Neve de Mevergnies and A. Paulsen in "Survey of Fusion Reactor 

" Technology", Report EUR 4873e (1972), p. 277.

JII.V 

III.C. 


.The priority criteria which appear in this section were 

developed by the Agency with the assistance of the 

International Fusion Research Council (iFRC), the INDC 

and many scientists engaged in fusion research. Presently 

they are the basis of the priority assignments for the 

requests from the United Kingdom and the Federal Republic 

of Germany. 

Priority Criteria for Nuclear Data Requests 

in Controlled Fusion Research (CFR) 

Priority 1 

In general highest (first) priority shall be assigned 

to those nuclear data upon which some important aspect of 

CFR is immediately contingent. Specifically Priority 1 

shall be assigned to requests for nuclear data which 

1. are required for evaluation of the feasibility of 

a proposed CF reactor concept or 

2. are required for immediate application of plasma 

phenomena in a fusion reactor context, or 

3. are essential for application of a material which is 

of conceptual importance in CFR, or 

4. are required for an important decision involving 

allocation of resources or redirection of research effort 

in CFR programmes, or 

5. are necessary to develop some important aspect of current 

CFR programmes to a level consistent with progress in 

other aspects of these programmes.

Ill.vi 

Priority 2 

Priority 2 shall be assigned to nuclear data which 

1. are required for evaluation of materials of high potential 

utility in current CF reactor designs, or 

2. are expected to contribute to significant progress in CFR 

or reactor design studies in the near future. 

Priority 3 


1. are of use in current design studies but are not of 

crucial importance, or 

2. are not of immediate importance for CFR but which have 

probability of becoming important as CFR programmes 

develop. 

Priority 4 


1. fill out the body of information needed for fusion 

reactor technology, or 

2. are of potential interest for CFR but which cannot bo 

assigned more definite priority at present.

Ill.vii 

III.D. 

Index to Fusion List 

TARGET 

PAGE 

1 HYDROGEN 2 

1 HYDROGEN 3 

2 HELIUM 3 

3 LITHIUM 6 

3 LITHIUM 7 

4 BERYLLIUM 9 

5 BORON 10 

6 CARBON 

6 CARBON 12 

6 CARBON 13 

7 NITROGEN 14 

8 OXYGEN 

9 FLUORINE 15 

13 ALUMINUM 27 

14 SILICON 

18 ARGON 40 

22 TITANIUM 

23 VANADIUM 

24 CHROMIUM 

2 4 CHROMIUM 52 

25 MANGANESE 55 

26 IRON 

26 IRON 54 

26 IRON 58 

28 NICKEL 

28 NICKEL 58 

2 8 NICKEL 60 

29 COPPER 

29 COPPER 63 

30 ZINC 66 

40 ZIRCONIUM 

41 NIOBIUM 53 

42 MOLYBDENUM 

47 SILVER 109 

74 TCNGSTEN 

82 LEAD 

82 LEAD 2 04 

83 BISMUTH 209 

90 THORIUM 232 

92 URANIUM 238 

ooooooooeoooooo 

OOOOOOOOOOOOOOO 

ooooooooooooooo 

OOOOOOOOOOOOOOO 

oooooooocoooooo 

oooooeooooooooo 









ooooooooeoooooo 





O 0 0 oooooooooooo 



















o o o o o o o o o o o o o o o 


He- 1 

llo 1 

IIo 1 

H o 1 

IIo 3 

IIo 4 

IIo 5 

IIo 5 

IIo 5 

IIo 5 

IIo 6 

IIo 6 

IIo 6 

IIo 7 

IIo 8 

IIo 8 

IIo 8 

IIo 8 

IIo 10 

IIo 11 

IIo 11 

IIo 11 

IIo 12 

IIo 12 

IIo 13 

IIo 13 

IIo 14 

IIo 14 

IIo 14 

IIo 15 

IIo 15 

IIo 15 

IIo 17 

IIo 18 

IIo 18 

IIo 19 

IIo 19 

IIo 19 

IIo 19 

IIo 20

III. E. 

DATA REQUEST LIST FOR FUSION REACTOR DEVELOPMENT

1 HYDROGEN 2 NEUTRCN N.2N 

15Z0S4 1 So 0 MEV 2 FR Ao MI CHAUDON BRC 

A: ACCURACY REQUIRED TO BETTER THAN 20 PERCENTo 


1 HYDROGEN 3 NIUTRCN N.2N 

112295 15o 0 MEV 2 FR AoMICHAUDON BRC 

A: ACCURACY. REQUIRED TO BETTER THAN 20 PERCENTo 


2 ~ HELIUM 3 NEUTRON N.F 

2-£25Sf 1o 00 KEV 15o 0 MEV lOoOX 1 FR AoMICHAUDON BRC 


STA TUS 

STATUS 

GA CO STELLO+ - NSE 39 409(1970). DATA 0o3 TO lol MEV WITH 10 PERCENT ACCURACYo 

GA COSTELLO* - 70 ANL 74(1970). REVIEWo 

GEL LISKIEN+ - 72VIENNA 135. FROM EVALUATION OF INVERSE REACTION, DATA Oo 2 TO 9 MEVo 

2 HELIUM 3 _ HELIUM-3 __ HELIUM-3,2P 

241245 1 OOo KEV So 00 MEV 1 SoOX 3 USA JoRoMC NALLY ORL 

0: TO EVALUATE ADVANCED FUELSo 

EVALUATION AND MEASUREMENTS NEEDEDo 


3 LITHIUM 6 NEUTRON ~olFFERENTIAL~ELASTIC CR0SS~SECT10N 

222260 lo 00 MEV 15o 0 MEV lOoOX 2 GER 'DoDARVAS JUL 

HoKUESTERS 

KFK 

Q: ADDITIONAL ANGULAR DISTRIBUTIONS ABOVE 6 MEV AND 

AN IMPROVEMENT IN ACCURACY BELOW 6 MEV REOUIREDo 

0: CALCULATION OF NEUTRON TRANSPORTo 

222061 1o 00 KEV 1 So 0 MEV 20oOX 3 UK RoHANCOX HAR 

0: FOR SHIELDING CALCULATIONSo 


224001 4o 00 MEV 15o 0 MEV lOoOX 2 CCP IoNoGOLOVIN KUR 

O: REFINEMENT OF DATA BELOW 7 MEV AND ADDITIONAL DATA 

ABOVE 7 MEV REQUlREDo 

0: CALCULATION OF NEUTRON TRANSMISSIONo 

2321101 1 4o 0 MEV lOoOX 1 FR DoBRETON FAR 

0: EVALUATION OF NEUTRON BALANCEo 

3_ LITHIUM 6 _ " NEUTRCN ~ ~ DOUEL E~ D7 FFERENTJ AL ~7NELA ST IC~CR0SS~ SECTI ON 

23Z11S ISoO MEV 20 o OX 3 UK RoHANCOX HAR 


3 LITHIUM 6 " "NEUTRON TOTAL~PHOTON"PRODUCT ION~CROSS~SECTTON 

12S00& 9o 00 MEV 15o 0 MEV ISoOX 2 CCP IONOGOLOVIN KUR 

O: GAMMA RAY PRODUCTION CROSS SECTIONS AND GAMMA RAY 

SPECTRA ARE REQUlREDo 

O: GAMMA RAY HEATING AND SHIELDING CALCULATIONSo 

5 LITHIUM E _ NEUTRON DOUBLE DIFFERINTIAL NiuTRON-EMIIILONCROIIIECTFON 

122264 1 So 0 MEV 20o0X 2 GER DoDARVAS JUL 

HoKUESTERS 

KFK 

Q: SECONDARY ENERGY AND ANGULAR DISTRIBUTIONS WANTEDo 

NEUTRON SPECTRA UP TO MAXIMUM ENERGIES ARE 

REQUIRED© 

NEUTRON ANGULAR DISTRIBUTIONS AT A FEW ENERGIES 

WOULD BE USEFULo 

O: FOR CALCULATIONS OF NEUTRON TRANSPORT AND 

SHIELDINGo 


1A1250 14o 0 MEV 1Oo OX 2 USA LoSTEWART LAS 

Q: SPECTRA AT SEVERAL ANGLES REQUlREDo 

MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo 


FUSION LIST PAGE IIIo 1

3 LITHIUM 6 

Z221S1 

1 5o 0 KEV 

lOoOX 

CODARVAS 

HoKUESTERS 

JUL 

KFK 

A: ENERGY RESOLUTION OF 0o2 TO Oo 5 MEV WOULD BE 

SUFFICIENTo 

0: FOR SHIELDING AND CALCULATION OF HEAT GENERATION 

Z2AQQ3 

ISoO 

MEV 

lOoOX 

P I0N0GOLOVIN KUR 

0: NEUTRON ICS CALCULATIONS AND ENERGY DEPOSITION IN 

BLANKET MATERIALSo 

3 LITHIUM 6 NEUTRCN 

2i2 062 3 OOo KEV 1 So 0 MEV SoOX OoDARVAS 

HoKUESTSRS 

JUL 

KFK 

0: TOTAL TRITIUM PRODUCTION REOUIREDo 

A: ENERGY RESOLUTION SHOULD REPRODUCE TRUE SHAPEo 

O: FOR DETERMINATION OF MORE ACCURATE TRITIUM 

BREEDING RATIOSo 

223002 1OOo KEV 3o 00 MEV CCP I0N0GOLOVIN KUR 

0: FOR TRITIUM BREEDING AND ENERGY DEPOSITION 

232002 3° 00 MEV IAo 0 MEV 5 o OX FR DoBRETON FAR 

0: FOR EVALUATION OF NEUTRON BALANCEo 

3 LITHIUM 6 NEUTRON 

1&211Q So 00 KEV ISoO MEV SoOX I GER MoKUECHLE KFK 

0: STANDARDo 



HAR UTTLEY* - AERE-FR/NP 19 5

3 LITHIUM 6 LITHIUM-6 LITHIUM-6.ALPHA 

141246 2 COo KEV SoOO MEV ISoOX JoRoMC NALLY ORL 

O: CROSS SECTION FOR PRODUCTION OF 3 ALPHA PARTICLES, 

o: TO EVALUATE ADVANCED FUELSo 

EVALUATION AND MEASUREMENTS NEEDEDo 


3 LITHIUM 7 DIFFERENTIAL ELASTIC CROSS SECTION 

122066 lo 00 MEV 

1 So 0 MEV 

OoDARvAS 

HoKUESTERS 

JUL 

KFK 

ADDITIONAL DISTRIBUTIONS BETWEEN 2 AND 

REQUIRED IN STEPS OF OoS TO 1 MEVo 

FOR CALCULATION OF NEUTRON TRANSPORTo 

122061 1o 00 KEV 

15o0 MEV 1 So OX 

RoHANCOX 

0: FOR SHIELDING CALCULATIONSo 


22400S 2o 00 MEV 1 So 0 MEV lOoOX P IoNo GOLOVIN KUR 

Q: REFINEMENT OF OATA BELOW 7 MEV AND ADDITIONAL OATA 

ABOVE 7 MEV REQUlREDo 

0: FOR TRITIUM BREEDING AND ENERGY DEFOSITIONo 

222003 1 Ao 0 MEV 1 OoOX FR CoBRETON FAR 

0: EVALUATION OF NEUTRON BALANCE, 

3 LITHIUM 7 

"1NELAST IC~CROSS~SECTloN 

122Q6S SOOo KEV 15,0 MEV lOoOX GER Do OARVAS 

HoKUESTBRS 

JUL 

KFK 

Q: CROSS SECTION FOR Oo 478 MEV LEVEL REQUlREDo 

0: FOR SHIELDING ESTIMATES AND CALCULATION OF HEAT 

GENERATION o 

224006 1 So 0 MEV 15, OX P IoNoGOLOVIN KUR 

a: CROSS SECTION FOR 0,478 MEV LEVEL REQUIRED, 

O: NEUTRON ICS CALCULATIONS AND ENERGY DEPOSITION, 

3 LITHIUM 7 NEUTRCN ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

122113 15,0 MEV 20,OX UK RoHANCOX 


3 LITHIUM 7 TOTAL PHOTON PRODUCTION CROSS SECTION 

224010 9,00 MEV 15,0 MEV 15,0X 1 CCP loNoGOLOVlKl KUR 

Q: GAMMA RAY PRODUCTION CROSS SECTIONS AND GAMMA RAY 

SPECTRA ARE REQUlREDo 


3 LITHIUM 7 NEUTRCN 

222021 15,0 MEV 20o0X DoDARVAS 

HoKUESTERS 

JUL 

KFK 

0: THREE OR FOUR OATA POINTS USEFUL, 

0: FOR ESTIMATES OF NEUTRON MULTIPLICATION, 

Z240QS 15,0 MEV P I oNo GOLOV IN KUR 

Q: SECONDARY ENERGY AND ANGULAR DISTRIBUTIONS AT 

14 TO 15 MEV REQUlREDo 

O: BLANKET NEUTRON ICS CALCULATIONSo 

3 LITHIUM 7 DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION 

241251 14,0 MEV lOoOX 1 USA LoSTEWART 

0: SPECTRA AT SEVERAL ANGLES REQUIRED, 



3 LITHIUM 7 NEUTRON NiNT 

122065 15,0 MEV OoDARVAS 

HoKUESTBRS 

JUL 

KFK 

RESOLUTION AND ENERGY STEPS OF ,2 TO ,5 MEV 

SUFFICIENT, 

DETERMINATION OF MORE ACCURATE TRITIUM BREEDING 

RATIOS, 

124002 15,0 MEV SoOX CCP IoNoGOLOVIN KUR 

O: FOR TRITIUM BREEDING AND ENERGY DEPOSITION, 

FUSION LIST PAGE III, 3

3 LITHIUM 7 NEUTRCA (CONTINUED! 

224S>i>B 1 Oo 0 MEV 1 So 0 MEV 1 So OX P IONOGOLOVIN KUR 

0: SECONDARY ENERGY AND ANGULAR DISTRIBUTIONS 

REQUIREDo 

O: NEUTRON TRANSMISSION CALCULATIONSo 

2.221104 3o 00 ME V !4o 0 MEV DoBRETON FAR 

O: EVALUATION OF NEUTRON BALANCEo 

3 LITHIUM 7 N, NALPHA 

24.1252 I So 0 MEV lOoOX DoDUDZIAK LAS 

Q: EVALUATION WITH UNCERTAINTY-FILES REQUIREDo 

O: TO CALCULATE TRITRI UM BREEDING - HIGH SENSlTIVITYo 

UNCERTAINTY FILES NEEDED TO PERFORM CROSS-SECTION 

SENSITIVITY STUDIES FOR FUSION DEVlCESo 


4 BERYLLIUM 9 NEUTRCN DIFFERENTIAL ELASTIC CROSS SECTION 

222322 1 o 00 MEV 15o 0 MEV GER OoDARVAS 

SoCIERJACKS 

JUL 

KFK 

0: CALCULATION OF NEUTRON TRANSPORTo 

224.Oil 2o00 MEV ISoO MEV CCP IoNoGOLOVIN KUR 

0: FOR NEUTRON TRANSMISSION CALCULATIONSo 

4 BERYLLIUM 9 INELASTIC CROSS SECTION 

22*012 ISoO MEV CCP IONOGOLOVIN KUR 

O: NEUTRON ICS CALCULATIONS FOR BLANKET AND SHIELDo 

4 BERYLLIUM 9 NEUTRCN DOUELE DIFFERENTIAL INELASTIC CROSS SECTION 

222524 8o 00 MEV ISoO MEV GER OoDARVAS 

SoCIERJACKS 

JUL 

KFK 

4 BERYLLIUM 9 NEUTRON PHOTON PRODUCTION CROSS SECTION IN INELASTIC SCATo 

222S2S Bo 00 MEV ISoO MEV lOoOX GER OODARVAS 

SOCIERJACKS 

JUL 

KFK 

o: ENERGY DISTRIBUTION OF GAMMA RAYS REQUIREDo 

4 BERYLLIUM 9 NEUTRON 

TOTAL PHOTON PRODUCTION' CROSS licTION 

224515 3o 00 MEv ISoO MEV ISoOX CCP IoNo GOLOVIN KUR 

o: GAMMA RAY SPECTRA ALSO REQUIREDo 

0: GAMMA RAY HEATING AND SHIELDING CALCULATIONSo 

4 BERYLLIUM 9 NEUTRCK 

222226 1 So 0 MEV 20o0X RoHANCOX HAR 

0: TO EVALUATE NEUTRON ECONOMY IN BREEDING 

CALCULATIONSo 


222522 1 So 0 MEV 

OoDARVAS 

SoCIERJACKS 

JUL 

KFK 

Q: 

0: 

ANGULAR DISTRIBUTIONS AND ENERGY SPECTRA OF 

SECONDARY NEUTRONS AND GAMMA RAYS ALSO NEEDEDo 

RADIATION DAMAGE ESTIMATE So 

224313 ISoO MEV IoNoGOLOVIN KUR 

0: ENERGY AND ANGULAR DISTRIBUTION OF SECONDARY 

NEUTRONS REQUIREDo 

0: USE FOR NEUTRON MULTIPLICATION AND TRANSMISSION 

CALCULATIONSo 

2525115 2o00 MEV 14o 0 MEV OoBRETON FAR 

TO IMPROVE NEUTRON BALANCE CAVCULATIONSo 

241254 ISoO MEV lOoOX DoOUDZIAK LAS 

Q: EVALUATION WITH UNCERTAINTY-FILES REQUIRED, 

O: SWELLING OF BERYLLIUM NEUTRON MULTIPLIER DUE TO 

TWO ALPHA-PARTICLE BREAK UPo 

HIGH SENSITIVITY OF TRITIUM BREEDING AND ENERGY 

PRODUCTION TO NEUTRON MULTIPLICATIONo 

UNCERTAINTY FILES NEEDED TO PERFORM CROSS-SECTION 

SENSITIVITY STUDIES FOR FUSION DEVlCESo 



4 BERYLLIUM_9_ __ _ NEUTRCN N.2N _ _ _ (CONTINUED) 

STATUS 

STATUS 

JUL BLOSER - AKE 2.0 309(1973), ABSOLUTE DATA FROM 2 = 4 TO 3o 2 MEVo 

FOA HOLMBERG+ - NF/A 129 305(1969), DATA 2 TO 6o4 MEVo 

4bIRYLL1UM 9 " NEUTBON DCUELE DIFFERENTIAL NEUTRON-EMI111 ON CROsi SECTION 

241252 14o 0 MEV lOoOX 1 USA Lo STEWART 

SPECTRA AT SEVERAL ANGLES REOUIREDo 


NEW REOUESTo 

4 BERYLLIUM 9 

2Z202& Bo 00 MEV 1 5o 0 MEV lOoOX 2 

GER DoDARVAS JUL 

So CIERJ ACK S 

KFK 

0: TOTAL ALPHA PRODUCTION REOUIREDo 

0: CALCULATION OF NEUTRON TRANSPORT© 

224314 Bo 00 MEV 15o 0 MEV 15oOX 2 

CCP IoNoGOLOVIN KUR 

O: FOR HELIUM ACCUMULATION CALCULATIONSo 

5 BORON 1C NEUTRCN 

N, 2N 

I22SQ6 Bo 00 MEV 14o 0 MEV 1SoOX 2 FR DoBRETON FAR 

0: FOR IMPROVED CALCULATION OF NEUTRON BALANCEo 

5~i0R0N~ia " NEUTRCN " N, 3N 

22ZS92 1 Co 0 MEV 14o 0 MEV ISoOX 2 FR DoBRETON FAR 

O: FOR IMPROVED CALCULATION OF NEUTRON BALANCE© 

6~CA5BON NEUTRCN OOUELEDIFFERENTIAL'NEUTRON-EMillION'CROSS SECTFON~ 

1&1Z5S Bo 00 MEV ISoO MEV lOoOX 2 USA VoJoORPHAN SAI 

FoGoPEREY 

ORL 

GoHOPKINS 

GA 

SPECTRA AT SEVERAL ANGLES REQUIRED, 


NEW REQUESTo 

6 CARBON 12 NEutRON DIFFERENTIAL ELASTIC CROSS SECTION 

22&S16 Be 00 MEV 15,0 MEV lOoOX 2 CCP I,N,GOLOVIN KUR 

0: NEUTRON TRANSMISSION CALCULATIONSo 

6 CARBON 12 * " NEUTRCN N, ALPHA 

2.24.1)12 15,0 MEV 15,OX 2 CCP IoNoGOLOVIN KUR 

O: NEUTRON ABSORPTION CALCULATIONSo 

6 _ CARION"li NEUTRCN ~N7N3ALPHA 

224515 15o 0 MEV 1 So OX CCP IoNoGOLOVIN KUR 

0: SECONDARY NEUTRON ENERGY DISTRIBUTION REQUIRED 

AT 14, MEV, 

O: FOR BLANKET NEUTRONICS CALCULATIONS, 

141ZS6 1 5, 0 MEV 10,OX Go HOPKINS 

V,JoORPHAN 

GA 

SA I 

o: 

M: 

TO CALCULATE HELIUM PRODUCTION, 

NEW REQUEST© 

241255 15,0 MEV A DoOUCZIAK LAS 

0 : TO CALCULATE HELIUM PRODUCTIONo 


6 CARBON 13 NEUTRCN CAPTURE CROSS SECTION 

24125S 25,3 MV 3,00 MEV 25oOX 2 USA VoJ,ORPHAN SAI 

GoHOPKINS 

GA 

0: PRODUCTION OF C-14 ACTIVITY, 


6~CAR80N~13 ~ NEUTRCN NTALPHA" 

2A12&0 15,0 MEV 25, OX 2 USA Vo JoORPHAN SA I 

GoHOPKINS 

GA 

0: PRODUCTION OF BE-10 ACTIVITY, 



7 NITROGEN 14 NEUTRCN OCUBLE DIFFERENTIAL NEUTRON-EMI SSI ON CROSS SECTION 

2U26X 1 4o O MEV lOoOX USA PoGoYOUNG LAS 

o: SPECTRA AT SEVERAL ANGLES REQUIREDo 

MUST RECORD NEUTRONS DOWN TO A FEW KEVo 


8 OXYGEN ANGULAR DIFFERENTIAL INELASTIC CROSS SECTION 

ZA1262 14o 0 ME.v USA PoGoYOUNG LAS 

Q: CROSS SECTION FOR THE FIRST TWO LEVELS IN 0-16 

REQUIRED (NEED NOT BE SEPARA TED)o 

MEASUREMENTS AT SEVERAL ANGLES NEEDEDo 


8 OXYGEN NEUTRON DOUBLE DIFFERENTIAL NEUTRON-EM ISSI ON CROSS SECTION 

2A1263 14o 0 MEV lOoOX USA PoGoYOUNG LAS 

O: SPECTRA AT SEVERAL ANGLES REQUIREDo 

MUST RECORD NEUTRCNS DOWN TO A FEW HUNDRED KEVo 


9 FLUORINE 19 NEUTRON DIFFERENTIAL ELASTIC CROSS SECTION 

222SIBS) loOO ME V 1 So 0 MEV lOoOX OoDARVAS 

SoCIERJACKS 

JUL 

KFK 

INCIDENT ENERGY STEPS FROM 10 TO 20 PERCENTo 

CALCULATION OF NEUTRON TRANSPORTo 

Z-2AE15 2o 00 MEV ISoO MEV 

1 OoOX CCP IoNoGOLOVIN KUR 

o: USE IN COOLANTo 

STA TUS- 

CRC CLARKE* - NF/A 147 174(1970). DATA AT 14o MEVo 

-STATUS 

ANL GUENTHER* - USNDC-3 13(1973). IN PROGRESS TO 4 MEVo 

9 FLUORINE 19 NEUTRCN INELASTIC CROSS SECTION 

12Z&BX lo 00 MEV 1SoO MEV lOoOX CoOARVAS 

SoCIERJACKS 

JUL 

KFK 

Q: INELASTIC EXCITATION FUNCTIONS REQUIREDo 

0: CALCULATION OF HEAT GENERATION AND SHIELDING 

ESTIMATESo 

222062 1 Oo 0 MEV 1 So 0 MEV 20o OX RoHANCOX HAR 

0: FOR APPLICATIONS USING FUSED SALT COOLANTo 


zz&aza loco MEV 1 So 0 MEV 1 SoOX CCP IoNo GOLOVIN KUR 

0: NEUTRON ICS CALCULATIONS FOR BLANKET AND SHIELDo 

9 FLUORINE 19 NEUTRON DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION 

Z .£2.68,3 loOO MEV 1Eo 0 MEV ZOoOX 1 GER DoDARVAS JUL 

SoCIERJACKS 

KFK 

STATUS 

ANL SMITH* USNCC-1 5(1972)o SCME DATA EELOW lo£ MEVo 


ESTIMATESo 

9 FLUORINE 19 NEUTRON ABSORPTION CROSS SECTION 

122S&2 2 So 3 MV 1 So 0 MEV RoHANCOX HAR 

O: DATA NEEDED FOR APPLICATIONS USING FUSED SALT 

COOLANTo 


Z2SJ>21 2 So 3 M V 1 So 0 MEV ISoOX CCP 1 oNoGOL'OV IN KUR 

0: ALL NEUTRON ABSORPTION PROCESSES SHOULD BE 

INCLUOEDo 

o: NEUTRON ICS CALCULATIONS AND ENERGY DEPOSITION IN 

COOLANTo 

ISZAAS 25,3 MV 

14o 0 MEV FR OoBRETON FAR 

O: UTILIZATION IN THE COOLANTo 

9 FLUORINE 19 

NEUTRCN 

PHOTON PRODUCTION CROSS .sicTION~IN TNELASTIC~SCATO~ 

Z220&9 loOO MEV 1 So 0 MEV 20o0X 1 GER DoDARVAS JUL 

SoCIERJACKS 

KFK 

O: ENERGY AND ANGULAR DISTRIBUTION OF GAMMA RAYS 

REOUIREDo 


ESTIMATESo 

FUSION LIST PAGE 1IIo 6

9 FLUORINE 19 NEUTRON _ TOTALPHOTON PRODUCTION CROSS SECTION 

Z2&&22 5OOo KEV 15o 0 MEV ISoOX 2 CCP IoNoCOLOVIN KUR 

O: GAMMA RAY SPECTRA ALSO REOUIREDo 

o: GAMMA RAY HEATING AND SHIELDING CALCULATIONSo 

5~FLUORINE~19 NEUTBON N.2N 

Z22SBS 15o0 MEV 20o OX RoHANCOX HAR 

O: TO EVALUATE NEUTRON ECONOMY IN BREEDING 

CALCULATIONSo 


9 FLUORINE 19 DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION 

ZA1264 900o KEV 1 So 0 MEV ISoOX USA FoGoPEREY ORL 

0: SPECTRA AT SEVERAL ANGLES REOUIREDo 



9 FLUORINE 19 TOTAL PROTON PRODUCTION CROSS SECTION 

ZA126S ISoO MEV FoGoPEREY 

0: CALCULATION OF HYDROGEN PRODUCTIONo 


9 FLUORINE 19 

Z22SB6 1 So 0 MEV lOoOX DoDARVAS 

So CIERJACKS 

JUL 

KFK 

0: CALCULATION OF NEUTRON ABSORPTION AND TRANSMISSION 

RATESo 

STATUS— . 

BIR CRUMPTON+ - NIK 92 533(1971). DATA 12 TO 15 MEVo 

9~FLUORINE19 NEUTRCN ' TOTALALPHA*PROOUCTloN CROSS'SECTION 

ZAX266 1 So 0 MEV 15o OX 1 USA FoGoPEREY 

0: CALCULATION OF HELIUM PRODUCTIONo 



Z-SJ.26.fi 1 So 0 MEV ISoOX 1 USA OoDUOZIAK LAS 

O: EVALUATION WITH UNCERTAINTY-FILES REOUIREDo 

O: NEEDED TO PREDICT GENERATION OF LONG-LIVED AL-26 

IN FTR STRUCTURES. COILS AND ALUMINUM OXIDE 

INSULATORSo 

UNCERTAINTY FILES REQUIRED TO PERFORM CROSS 

SECTION SENSITIVITY ANALYSIS FOR FUSION DEVICESo 


13~ALUMTNUM~27~ * NEUTRON 

DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION 

ZS126S 1 4o 0 MEV USA PoGoYOUNG LAS 

Q: SPECTRA AT SEVERAL ANGLES REQUIREDo 




Z41262 1 So 0 MEV ISoOX DoOUDZIAK LAS 

Q: 

O: 

M: 

EVALUATION WITH UNCERTAINTY FILES REQUlREDo 

NEEDED TO CALCULATE HEAT GENERATION IN AL 

STRUCTURES DUE TO SHORT-LIVED TRANSMUTANTS 

(MG-27) SHORTLY AFTER SHUTQOWNo 

HIGH AFTERHEAT POWER DENSITY MAY CAUSE AL 

STRUCTURES TO MELT IN CASE OF LOSS-OF-COOLANT 

ACCIDENT, 

FERF APPLICATIONSo 


SECTION SENSITIVITY ANALYSIS FOR FUSION DEVICESo 

NEW REQUESTo 

STA TUS— 

' 

-STATUS 

NOC SCHETT+ - EANCOSS (197*). COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974o 

ANL SMITH* - ANL/NDM-10 (1975). MEASUREMENTS AND EVALUATION FROM 2o8 TO 10 MEVo 

13 ALUMINUM 27 NEUTRON TOTAL PROTON PRODUCTION CROSS SECTION 

ZU.2Z6 15o 0 MEV 1 So OX USA CoOUCZIAK LAS 

Q: EVALUATION WITH UNCERTAINTY-FILES REQUlREDo 

O: EVALUATION OF RADIATION DAMAGE IN AL COILS AND 

STRUCTURESo 

UNCERTAINTY FILES REQUIREO TO PERFORM CROSS 

SECTION SENSITIVITY ANALYSIS FOR FUSION DEVICESe 



13 ALUMINUM 27 NEUTRON TOTAL PROTON PRODUCT ION CROSS SECTION (CONTINUED! 

1A1Z12 1 So 0 MEV 1 So OX 2 USA RoHAIGHT LRL 

O: HYDROGEN PRODUCTION REOUIREDo 


13 ALUMINUM 27 NEUTRON TOTAL ALPHA PRODUCT ION CROsi IECTION 

2£U22& 1 SoO MEV ISoOX 2 USA RoHAIGHT 

0: HELIUM PRODUCTION REQUIREOo 


2A1Z2S 1 So 0 MEV ISoOX 2 USA DoDUDZIAK LAS 

0: EVALUATION WITH UNCERTAINTY-FILES REOUIREDo 

0: EVALUATION OF RADIATION DAMAGE IN AL COILS AND 

STRUCTURESo 


SECTION SENSITIVITY ANALYSIS FOR FUSION DEVlCESo 


14 SILICON NEUTRON DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION 

24122S BoOO MEV 1 So 0 MEV lOoOX 2 USA Go HOPKINS GA 

VoJoORPHAN 

SAI 

O: MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo 


14 SILICON NEUTRON TOTAL ALPHA PRODUCT ION CROSS SECTION 

2312B0 ISoO MEV ISoOX Go HOPKINS 

VoJoORPHAN 

GA 

SAI 

HELIUM PRODUCTION REQUIREOo 

NEW REQUESTo 

18 ARGON 4C NEUTRCN 

2A12B2 1 So 0 MEV ISoOX USA DoDUDZIAK LAS 

Q: EVALUATION REQUIREDo 

O: TO EVALUATE AR-39 PRODUCTION IN AIR AROUND FUSION 

TEST REACTORSo 


22 TITANIUM NEUTRGN INELASTIC CROSS SECTION 

222MS 3o 00 MEV 14o 0 MEV FR DoBRETON FAR 

0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo 

22 TITANIUM NEUTRCN 

ZZZSIO 14o 0 MEV lOoOX 3 FR DoBRETON FAR 


22 TITANIUM NiuTRCN N.P 

222S11 14o 0 MEV lOoOX 3 FR DoBRETON FAR 

o: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo 

22 - TITANIUM " " ""NEUTRON ~ NTALPHA 

232212 14o 0 MEV lOoOX 3 FR DoBRETON FAR 

O: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo 

I5"ANADIUM NEUTPCN ELASTIC'CROSI"SECT ION 

= 

224223 2o 00 MEV ISoO MEV lOoOX 1 CCP IoNoGOLOVIN 

O: POTENTIAL USE AS STRUCTURAL MATERIALo 

FOR DETERMINATION OF NEUTRON TRANSMISSIONo 

23 VANADIUM NEUTRCN INELASTIC CROSS SECTION 

3o 00 MEV 14o0 MEV lOoOX 2 FR Do BR ETON FAR 


IA'VANADIUM - ~ NEUTRON EN1RGY~CIFPIRINTIAL~INILAITIC"CR0I5~SECTl5N 

Z2A2ZA 2o 00 MEV ISoO MEV 15oOX 1 CCP IONOGOLOVIN KUR 

0: NEUTRON ICS CALCULATIONS FOR BLANKET AND SHIELDo 

FUSICN LIST PAGE I lie 8

23 VANADIUM NEUTRCN ENERGY DIFFERENTIAL INELASTIC CROSS SECTION (CONTINUED) 

STATUS— 

STATUS 

AE ALMEN* - 7C HELSINKI 2 349(1970)• 15 LEVELS FROM 2 TO 4o5 MEV 

ANL SMITH* - USNDC-7 9(1973). WCRK IN PROGRESS TO 4 MEVo 

23 VANADIUM " ~ NEUTRCN CAPTURE CRois SicTIQN 

ZZ4SZ2 loOO KEV 2o 00 MEV 1 SoOX 1 CCP 

o: 

IoNoGOLOVIN 

KUR 

NEUTRON ABSORPTION. GAMMA RAY HEATING, AND 

PRODUCTION OF HIGHER I SOTOPESo 

zz&azs i Ao o MEV 1 5o OX 1 CCP 

0: 

IoNoGOLOVIN 

KUR 

NEUTRON ABSORPTION. GAMMA RAY HEATING. AND 

PRODUCTION OF HIGHER I SOTOPESo 

RPI STIEGLITZ : - NF/A 1C3 592(1971). DATA 100 EV TO 200 KEVo 

ORL MACKLIN* - LSNDC-3 148(1972). DATA 3 TO 500 KEV IN PROGRESSo 

HAR COATES - MEASUREMENT PLANNED FOR LATE 197=o 

23 VANADIUM NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION 

2Z3SZS 300o KEV 15o 0 MEV 1 SoOX 1 CCP 

o: 

o: 

IONOGOLOVIN 

KUR 

GAMMA RAY SPECTRUM ALSO »ANTEDo 

GAMMA RAY HEATING CALCULATIONSo 

Z41Z2A 8o00 ME V ISoO MEV ' 1SoOX 3 USA 

M: 

FoGoPEREY 

NEW 

REQUEST, 

ORL 

23 VANADIUM NEUTRCN N, 2N 

22S0ZZ 2o 00 MEV ISoO MEV ISoOX 1 CCP 

o: 

IoNoGOLOVIN 

KUR 

NEUTRON BLANKET CALCULATIONS, 

Z2&Q&6 14o 0 MEV 1 SoOX 1 CCP 

o: 

o: 

IONOGOLOVIN 

KUR 

ENERGY AND ANGULAR DEPENDENCE OF SECONDARY 

NEUTRONS REOUIREDo 

NEUTRON BLANKET CALCULATIONSo 

Z.22.013 14o 0 MEV lOoOX 2 FR 

o: 

0,BRETON 

FAR 

POTENTIAL CONSTITUENT OF CONTAINMENT VESSEL, 

23 VANADIUM NEUTRCN DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION 

ZH2B3 SoOO MEV 1 5o 0 MEV 1 5oOX 3 USA 

o: 

M: 

FoGoPEREY 

ORL 


NEW REQUESTo 

23 VANADIUM NEUTRCN N, F 

229.03.0 1 5o 0 MEV 1 5o OX 1 CCF 

IoNoGOLOVIN 

KUR 

o: 

FOR HYDROGEN ACCUMULATION CALCULATIONSo 

Z22SU.S 14o 0 MEV lOoOX 2 FR 

DoBRETON 

FAR 

o: 

POTENTIAL CONSTITUENT OF CONTAINMENT VESSEL, 

23 VANADIUM NEUTRCN TOTAL PROTON PRODUCTION CROSS SECTION 

ZAlifli ISoO MEV 1 So OX 3 USA 

o: 

M: 

FoGoPEREY 

ORL 

HYDROGEN PRODUCTIONo 

NEW REQUESTo 

23 VANADIUM NEUTRCN N,ALPHA 

1 So 0 MEV ISoOX 1 CCP 

o: 

IoNoGOLOVIN 

KUR 

HELIUM ACCUMULATION CALCULATIONSo 

14o 0 MEV lOoOX 2 FR 

OoBRETON 

FAR. 

o: 

POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo 

23 VANADIUM NEUTRON TOTAL ALPHA PRODUCTION CROSS SECTION 

ZA12BS ISoO MEV ISoOX 3 USA FoGoPEREY ORL 

•NEOSSASSEASCSS: 

o: 

M: 

HELIUM PRODUCTIONo 

NEW REOUESTo 

FUSICN LIST PAGE IIIo 9

24 CHROMIUM NEUTRCN TOTAL CROSS SECTION 

2A122S, 1 o 00 MEV 1 So 0 MEV USA CoDUOZIAK LAS 

o: EVALUATION WITH UNCERTAINTY-FILES REQUIREDo 

0: UNCERTAINTY FILES NEEDED TO PERFORM CROSS SECTION 

SENSITIVITY ANALYSIS FOR NEAR-TERM FUSION 

OEVICESo 


STATUS- 

-STATUS 

KFK 

TUD 

BET 

ANL 

SChATZo - KFK-1668 (1572), REVIEWo 

.TRAN UNG+ - ZF K—243(1972), DATA 3oI MEVo 

GREEN* - »APD-TM-1073(1973). DATA 0o5 TO 10 MEVo 

WHALENo- CATA TC lo5 MEV WITH 2-KEV RESOLUTICNo 

24 CHROMIUM NEUTRCN INELASTIC CROSS SECTION 

222012 3o 00 MEV 14o 0 MEV lOoOX FR CoBRETON FAR 


24 CHROMIUM 

NEUTRCN ABSORPTION CROSS SECTION 

Z&122S 1o 00 MEV 

ISoO MEV USA DODUDZIAK LAS 

o: EVALUATION WITH UNCERTAINTY-FILES REQUIREOO 

0: UNCERTAINTY FILES NEEDED TO PERFORM CROSS SECTION 


OEVICESo 


24 CHROMIUM TOTAL PHOTON PRODUCTION CROSS SECTION 

241230 1 o 00 KEV 20 o 0 MEV 20o0X 2 USA MoBhAT 


STATUS 

CCP DEGTJAREV* - IZV 35 2341(1571), DATA 1 TO 3o4 MEVo 

24 CHROMIUM NEUTRCN N, 2N 

22201s 14o 0 MEV lOoOX FR OoBRETON FAR 


24 CHROMIUM* DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION 

lilZZl 14o0 MEV 

1 SoOX USA RoHAIGHT LRL 

Q: SPECTRA AT SEVERAL ANGLES REQUIREDo 


24 CHROMIUM 'NEUTFCN - 

2220XS 14o 0 MEV lOoOX FR DoBRETON FAR 


UK UKNDC - AVAILABLE ESTIMATES OF FISSICN SPECTRUM AVERAGE DIFFER BY A FACTOR OF 5. MAINLY DUE TO 

UNCERTAINTY -IN CR-50IN,F)o 

24 CHROMIUM TOTAL PROTON PRODUCTION CROSS SECTION 

2&12SJ ISoO MEV 1SoOX 2 USA RoHAIGHT 

O: HYDROGEN PRODUCTION REQUIREOo 


24 CHROMIUM NEUTRCN 

2£202£ 14e0 MEV 10.OX 3 FR .Oo BRETON FAR 


STATUS—— —:—> STATUS 

AE WE ITHAN* - ANS 13 558(1970). HE PRODUCTION IN A FISSION SPBCTRUMo 

ALO FREEMAN* - .JNE 23 713(19691 , FISSION SPECTRUM AVERAGE. 

24~CHROMIUM NEUTRON " TOTAL~ALPHA~PRo5uCTION - CROSS~SECTION 

2H22S 15o 0 MEV ISoOX 2 USA RoHAIGHT LRL 

O: HELIUM PRODUCTION REQUIRED. 


FUSION LIST PAGE IIlo 10

24 CHROMIUM 52 

20o0 MEV 25o OX USA M,BHAT BNL 

O: NEEDED FOR EVALUATIONo 


STATUS 

JYV HOLMBERG* - Jll> 36 71 5(1974), DATA AT 14o7 MEVo 

24 CHROMIUM 52 

NEUTRON 

N.ALPHA 

241232 

20,0 MEV 25eOX USA MoBHAT 

O: NEEDED FOR EVALUATION© 


2 5 MANGANESE 55 NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION 

241232 I o OO KEV 20,0 MEV 20o0X USA M,BHAT 


25 MANGANESE 55 NEUTRCN 

141232 20,0 MEV 15,OX USA DoDUDZlAK LAS 

Q: EVALUATION WITH UNCERTAINTY-FILE IS REQUIRED, 

O: TO EVALUATE LONG-LIVED ACTIVITION OF CAPACITORS 

AND MAGNETIC MATERIALS IN THETA-PINCH FTP 

AND STEEL STRUCTURES IN NEAR-TERM FUSION DEVICES 

RADIATION DAMAGE ANALYSISo 


Z&lZSt 15,0 MEV 15,OX 2 USA RoHAIGHT LRL 

Q: EVALUATION REQUESTEDo 

0: NEEDED FOR FERF DESIGN, 


STA TUS— — 

-STATUS 

NDC SCHETT* - EANCC-95 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974, 

26 IRON INELASTIC CROSS SECTION 

222102 15,0 MEV 20,OX UK RoHANCOX HAR 

o: FOR BLANKET HEATING CALCULATIONS, 

222021 3,00 MEV 14,0 MEV 1OoOX 2 FR DoBRETON FAR 


26 IRON NEUTRON ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 

fiSjJlflfl Bo 00 MEV 15o0 MEV 20,OX 

GER BoGOEL KFK 

A: ENERGY RESOLUTION 500 KEV FOR INCIDENT NEUTRONS 

AND 200 KEV FOR SECONDARY NEUTRONS 


STATUS- 

ORL 

AE 

CSE 

ANL 

USA 

KINNEY* » 0FNL»4515 (1970). DATA 4 TO 8,5 MEV, 

ALMEN* - INDCtSEC)—31 39(1973). DATA 2 TO 4,5 MEVo 

LINDOW* - NCSAC-31 (1970). OATA 5 TO 5,5 MEV, 

SMITHo (1974). CATA TO 4 MEVo 

USNBC, (1974). CONSIDERS DATA WITH Ifr PERCENT ACCURACY PROBABLY AVAILABLE UP TO 4 MEV, 

26 IRON NEUTRON PHOTON PRODUCT ION CROSS SECTION IN INELASTIC SCAT, 

222103 15,0 MEV 20O0X UK ReHANCOX HAR 

O! FOR BLANKET HEATING CALCULATIONS, 


132120 1 5o 0 MEV RoHANCOX HAR 

0: ENERGY AND ANGULAR DISTRIBUTION OF GAMMA RAYS 

WANTEDo 



26IR0N _ NEUTRON _ _ TOTAL ^PHOTON PRODUCTION_CROSS SECTION (CONTINUED* 

STATUS 

STATUS 

ORL DICKENS - PR/C 5 100(1572). DATA FROM 5o3 TO 9 MEVo 

CCP KRAVCOV* - 72 KIEV (1972)o 

GA ORPHAN* - GULF-RT-10743 (1971). DATA FROM =9 TO 16o7 MEVo 

KFK VOSS+ - 71 KNCXVILLE 218(1971). DATA 08 TC 13 MEVo 

IRT HARRIS* - WCFK IN PROGRESS 4 TO IS MEV AT 125 DEGREESo 

26 IRON " NEU1RCN " N.2N 

222JOfi 1 So 0 MEV lOoOX 3 UK RoHANCOX HAR 

o: FOR NEUTRON ECONOMY CALCULATIONSo 



26 IRON NEUTRON INIFIGY OIFFERINTIAL NIUTRON-EMI 5SION CROsi'sECTION 

ZS.l.Zfl.8 8o 00 MEV 1 So 0 MEV 1 SoOX 2 USA FoGoPEREY ORL 

0: MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo 


2 6"I RON NEUTRCN N.P 

222101 ISoO MEV 20o0X 3 UK RoHANCOX HAR 

O: FOR HYDROGEN GAS PRODUCTION RATESo 

222022 14o 0 MEV ICoOX 2 FR OoBRETON FAR 


22210S 1 So 0 MEV 20o0X 3 UK RoHANCOX HAR 

O: FOR HELIUM GAS PRODUCTION RATESo 

2320Z4 14o 0 MEV lOoOX 2 FR DoBRETON FAR 


STA TUS— 

STATUS 

AE WEITMAN* - ANS 13 558(1970). HE PRODUCT ION IN A FISSION SPECTRUMo 

ALD FREEMAN* - JNE 23 713(1969). FISSION SPECTRUM AVERAGEo 

26 TRON NEUTRON _ ~ TOTAL ALPHA~PRODUCTLON'CROII SECTION 

2412BS 15o 0 MEV ISoOX 2 USA RoHAIGHT LRL 

O: HYDROGEN PRODUCTION REOUIREDo 


IA129Q ISoO MEV 1 So OX 2 , US A RoHAIGHT LRL 

0: HELIUM PRODUCTION REQUIREDo 


26~IRON 54 " SIUTRCN NTF ~ 

J41231 15o 0 MEV 

0: PRODUCTION OF MN-54o 


STATUS -> — STATUS 

GEL PAUL SEN* - 71CANTERBY 129(1971 ). CATA 1 TO 17 MEVo 

JUL • QAIM+ - 71CANTERBY 121(1971). DATA AT 15 MEVo 

NDC SCHETT* - EANCC-95 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 19740 

ANL SMITH* - ANL/NDM-10 (1975), MEASUREMENTS AND EVALUATION FROM lo9 TO 10 MEVo 

26 IRON IE "NEUTRON " " CAPTURE CRoli EECTION ~ * 

241232 ISoO MEV ISoOX 2 USA JoDoLEE LRL 

0: PRODUCTION OF FE-59o 


STATUS— 

STATUS 

RPI HOCKENBURY* - AiSNDC-3 155(1972) . WORK IN PROGRESS Oo 1 TO 200 KEVo 

KFK BEER* - EANCC(H)-157 (1973), EXPERIMENT PLANNEOo 


28 NICKEL NEUTRCN TOTAL CROSS SECTION 

2&12S2 1o 00 ME V 1 So 0 MEV 1 USA CoDUOZIAK LAS 

O: EVALUATION *ITH UNCERTAINTY-FILES REOUIREOo 

o: UNCERTAINTY FILES NEEDED TO PERFORM CROSS-SECTION 


DEVICESo 

M: NE* REOUESTo 

STATUS—.1: . STATUS 

ANL GUENTHER+ - VSNCC-11 17

28 NICKEL 56 (CONTINUED) 

Z312SS 1 5o 0 MEV 15o0X USA RoHAIGHT LRL 

O: EVALUATION REOUESTEDo 

O: NEEDED FOR LLL FERF DESIGNo 


-STATUS 

I RK 

GEL 

NDC 

ANL 

WAGNER* - AFA 37 288(1973). DATA 2 TO 20 MEVo 

PAULSEN* - EANDC(E)-150 (1972), MEASUREMENT IN PROGRESSo 

SCHETT* - EANBC-95 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974o 

SMITH* - ANL/NCk-10 (1975). MEASUREMENTS AND EVALUATION FROM Oo 4 TO 10 MEVo 

28 NICKEL 56 NEUTRON N. NP 

INSAS 1 So 0 MEV 15oOX RoHAIGHT LRL 

TOTAL PRODUCTION OF CO-57 REQUIRED (INCLUDING 

(N.D) REACTION )0 

EVALUATION REQUESTEDo 

NEW REQUESTo 

28 NICKEL 60 NEUTRCN N.ALPHA 

241321 20o 0 MEV 20o0X USA MoBHAT 


29 COPPER NEUTRON TOTAL CROSS SECTION 

2S1222 loOO MEV ISoO MEV CoDUDZIAK LAS 

Q: EVALUATION WITH UNCERTAINTY-FILES REOUIREDo 

O: UNCERTAINTY FILES NEEDED TO PERFORM CROSS-SECTION 


DEVlCESo 


29 COPPER NEUTRCN ELASTIC CROSS SECTION 

224232 So 00 PEV 15o 0 MEV CCP IoNoGOLOVIN KUR 

O: NEUTRON TRANSMISSION CALCULATIONSo 

29 COPPER ABSORPTION CROSS SECTION 

Z&lj&a lo 00 PEV 15o 0 MEV USA OoDUDZIAK LAS 

Q: EVALUATION WITH UNCERTAINTY-FILES REOUIREDo 

0: UNCERTAINTY FILES NEEDED TO PERFORM CROSS-SECTION 


DEVlCESo 


29 COPPER NEUTRON PHOTON PRODUCTION CROSS SECTION IN INELASTIC SCATo 

224232 ISoO MEV 1 5oOX CCP IoNoGOLOVIN KUR 

O: NEUTRON ICS CALCULATIONS FOR BLANKET AND SHIELOo 

29 COPPER TOTAL PHOTON PRODUCT ION CROSS SECTION 

224234 SOOo KEV 15o 0 MEV CCP IoNoGOLOVIN KUR 

0: GAMMA RAY SPECTRA ALSO WANTEOo 


1o 00 MEV 15o 0 MEV A VoJoORPHAN SAI 

O: EVALUATION ONLY TO INCORPORATE NEW DATAo 

0: FOR CALCULATING GAMMA-RAY HEATING IN COILSo 


29 COPPER 

22423£ 1 5o 0 MEV ISoOX CCP IoNoGOLOVIN KUR 

0: HYDROGEN ACCUMULATION CALCULATIONSo 

29 COPPER NEUTRCN 

223236 15o0 MEV CCP IONOGOLOVIN KUR 

0: HELIUM ACCUMULATION CALCULATIONSo 

29 COPPER 63 NEUTRON CAPTURE CROSS SECTION 

241321 2 So3 MV 2o 00 MEV ISoOX JoOoLEE LRL 

Q: ACTIVATION REQUIREDo 

EVALUATION ONLYo 

0: PRODUCTION OF CU-64o 



29 COPPER 63 NEUTRCN CAPTURE CROSS SECTION (CONTINUED) 

STATUS . —STATUS 

HAR MOXON* - AERE--PR/NP13 (1968). MEASUREMENTS IN PROGRESS TO 100 KEVo 

ORL MACKLIN* - NCSAC-42 185(1971). MEASUREMENTS IN PROGRESS TO 500 KEVo 

RPI PANDY* - DATA BEING ANALYZEOo 

29 C0PPER _ 63 ~ NEUTRON N7? 

JtiJOS 15o0 MEV ISoOX 1 USA DcOUDZIAK LAS 

0: ACTIVATION REOUIREDo 

EVALUATION WITH UNCERTAINTY-FILES REOUIREDo 

O: TO CALCULATE LONG-TERM ACTIVATION OF COPPER COILS 

IN FUSION DEVICES (NI-63. HALF-LIFE = 100 

YEARS)o 

RADIATION DAMAGE ANALYSIS, 


29^COPPER~63 NEUTRCN _ ~N7ALPHA 

ZAljflj ISoO MEV ISoOX 1 USA OoOUDZIAK LAS 

Q: ACTIVATION REQUlREDo 

EVALUATION WITH UNCERTAINTY-FILES REQUIRED, 

O: TO CALCULATE LONG-TERM ACTIVATION OF COPPER COILS 

IN FUSION DEVICES (C0-60. HALF-LIFE = 5,3 YEARS) 

RADIATION DAMAGE ANALYSIS, 


STA TUS ' STATUS 

GEL LISKIEN+ - JNE 27 39(1973). DATA AT 8,1 MEV, 

HAM BORMANN+ - NP/A 186 65(1972), DATA AT 14 MEVo 

NDC SCHETT+ - EANDC-95 (1974), COMPILATION OF EXPERIMENTAL OATA AVAILABLE AS OF JANUARY 1974o 

30 ZINC CC NEUTRCN N75N~ 

24A2B£ 15o 0 MEV 15,OX 2 USA RoHAIGHT LRL 

O: PRODUCTION OF ZN-65 REQUIRED, 

EVALUATION REQUESTED, 


40 ZIRCONIUM ~~' NEUTRGN ELAITIC"CROII~IICTION 

ZZ3.A32 5,00 MEV 15,0 MEV lOoOX 2 CCP IONOGOLOVIN KUR 

0: NEUTRON TRANSMISSION CALCULATIONS, 

40 ZIRCONIUM NEUTRON" ENERGY'DIFFIRENTIAL"INELAITic'CROIS'iEcTioN 

Z24S3J8 15,0 MEV 15, OX 2 CCP I oNo GOLOV IN KUR 

0: NEUTRON ICS CALCULATIONS FOR BLANKET AND SHIELD, 

40_ZTRCONIUM NEUTRON _ TOTAL~PHOTON PROOUCTION - CROSSSECTION 

226233 15,0 MEV ISoOX 2 CCP IoNoGOLOVIN KUR 

0: GAMMA RAY HEATING AND SHIELDING CALCULATIONS, 

40 ZIRCONIUM NEUTRON N71N 

224BSI1 15,0 MEV ISoOX 2 CCP I,N,GOLOVIN KUR 

0: FOR NEUTRON MULTIPLICATION CALCULATIONS, 

40 ZIRCONIUM = ==P= = * = NEUTRGN~ N7F 

22ASAi 15,0 MEV ISoOX 2 CCP IoNoGOLOVIN KUR 

0: HYDROGEN ACCUMULATION CALCULATIONS, 

40 ZIRCONIUM* = ~ = NEUTRON 57 ALPHA 

22A&A2, 15.0 MEV 15eOX 2 CCP IoNoGOLOVIN KUR 

0: HELIUM ACCUMULATION CALCULATIONS, 

41 NTOBTUM~S3 ^NEUTRON _ BIfFERENTI AL~ ELAStIC CRoll~iEcTION " =-=«= =- 

222X23 1,00 MEV 15,0 MEV 10.OX 2 GER DoOARVAS JUL 

HoKUESTERS 

KFK 

O: ANGULAR DISTRIBUTIONS AT A FEW SELECTED ENERGIES 

WOULD BE SUFFICIENTo 

O: RADIATION DAMAGE ESTIMATESo 

ZZAflti 3oOO MEV ISoO MEV l«rOX 1 C

41 NIOBIUM 93 NEUTRGN INELASTIC CROSS SECTION 

2221Z£ 15o 0 MEV lOoOX 2 GER DoDARVAS JUL 

HoKUESTERS 

KFK 

Q: FORMATION OF 13,6 YEAR ISOMER WANTEDo 

0: CALCULATION OF HEAT GENERATION AND RADIOACTIVE 

AFTERHEATo 

STATUSr-— 

STATUS 

AID COLES - AHRE/0-66/71, CATA 1 TO 5 MEVo 

AE ETEMADo - AE-461 (19731. DATA 2o0 TO 4o6 MEVo 

NDC SCHETT+ - EANDC-SS (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 197*o 

41~Nl55lUM~93 " ~ "NEUTRQN ENERGY~olFFiRiNTIAL - TNELAiTlE~CROSS iicTION ' 

224044 1 So 0 MEV ISoOX 1 CCF IONOGOLOVIN KUR 

O: NEUTRON CALCULATIONS FOR BLANKET AND SHIELDo 

41 NI OB I°UM~S3 _ NEuTRON DOUILE DIFFERENT IAL INELASTIC CRoli SECTION 

Z2212S 1o 00 MEV 1SoO MEV 20o0X 2 GER OoDARVAS JUL 

HoKUESTERS 

KFK 

• : RADIATION DAMAGE EST IMATE So 

41_NI0BIUM 53 _ NEUTRCN_ CAPTURE CROsi sEcTION 

224042 1Oo 0 MEV ISOO MEV ISoOX 1 CCF IONOGOLOVIN KUR 

0: HEAVIER ISOTOPE ACCUMULATION CALCULATIONSo 

STA TUS 

STATUS 

ORL MACKLINo - (1974 I, DATA TC 700 KEVo 

ANL POENITZo - ANL/NDM-8 (1974). DATA 0o3 TO 2oS MEVo 

HAR COATES - MEASUREMENT PLANNEDo 

41 - NIOIIUM~93 ' NEUTRON PH0T0N~PR50UCTl6N~CR0i5~SECTI0N~TN~INELASTIc"iCATo 

122130 lo 00 MEV ISoO MEV 20o0X GER OoDARVAS JUL 

HoKUESTERS 

KFK 

O: ENERGY AND ANGULAR DISTRIBUTION OF GAMMA RAYS 

REQUIREDo 

0: RADIATION DAMAGE ESTIMATESo 

41~NI0BIUM 53 NEUTRON TOTAL~PHOTON~PROCUCTION~CROSS~SECTTON 

1 So 0 MEV ISoOX 1 CCF IONOGOLOVIN KUR 


STATUS 

STATUS 

ORL DICKENS* - NCSAC-42 155(1971), IN PROGPESSo 

41 NIO5LUM53 -*«*" NEUTRCN _ N.2N 

222134 1 So 0 MEV lOoOX 2 GER DoCARVAS JUL 

HoKUESTERS 

KfK 

Q: A MEASUREMENT COUNTING THE OUTCOMING NEUTRONS 

WOULD BE PREFERRED TO CLARIFY THE SITUATION OF 

HITHERTO UNOBSERVED DECAY MODE So 

0: FOR RADIATION DAMAGE ESTIMATES, 

224042 15o 0 MEV lOoOX 1 CCP IoNoGOLOVIN KUR 

a: ENERGY AND ANGULAR DEPENDENCE OF SECONDARY 

NEUTRONS REOUIREDo 

O: FOR NEUTRON MULTIPLICATION AND RADIATION DAMAGE 

ESTIMATESo 

STATUS 

: 

— STATUS 

KFK KUSTERSo - (1572)o PRESENT RESULTS OBTAINEC BY COUNTING 0o93 MEV GAMMA RAYS FROM ZR-92 

FOLLOWING DECAY OF 10o2-0AY NB-92o A 3o 2-HOUR NB-92 ISOMER IS ALSO REPORTEDo SYSTEMATICS AND 

STATISTICAL Tt-EORY INDICATE TOC LOW CROSS CROSS SECTION PERHAPS DUE TO UNOBSERVED OECAYo 

HAR BLGWo - JNE 26 9(1972), DISCUSSION OF DISCREPANCY BETWEEN THEORY AND EXPERIMENT, 

NDC SCHETT* - EANDC-55 (1974). COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS OF JANUARY 1974, 

ANL SWITH* • ANL/NCM-6 (1974). EVALUATION FROM 12 TO 20 MEV, 

4l~~NioiiUM~53 NEUTPCN " N, 2N SIuTRON SPECTRA 

Z - U j l j 20,0 MEV 15,OX 2 USA OoDUDZIAK LAS 

O: EVALUATION REQUIRED, 

0: RECOIL SPECTRUM IMPORTANT FOR RADIATION DAMAGE, 

NB-92 AND NB-92M IMPORTANT IN RADIOACTIVITY AND 

AFTER-HEAT FOR SYSTEMS STUDIES, 


* NCHOEANESXEOEOEAEEOEE E*•AENEOE•BE*EEHEAA*EOHONBOEONGAHHAHAHO»HE EA AEOEOEOMGC»O=EAOOOC^C33EBBSAOEABOSAEEOCR 


41 NIOBIUM 53 NEUTRON DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION 

Z3JU0.S 1 4O 0 MEV 1 Oo OX LoSTEWART LAS 

SPECTRA AT SEVERAL ANGLES WANTEOo 


NEW REOUESTo 

41 NIOBIUM 53 NEUTRCN 

22213£ 3o 00 MEV ISoO MEV 20o0X SEP DoDARVAS 

HoKUESTERS 

JUL 

KFK 

O: RADIATION DAMAGE ESTIMATES. CALCULATION OF 

TRANSMUTATION RATES AND RADIOACTIVE AFTERHEATo 

Z23346 ISoO MEV ISoOX CCP IONOGOLOVIN KUR 

O: HYDROGEN ACCUMULATION CALCULATIONSo 

41 NIOBIUM 53 TOTAL PROTON PRODUCTION CROSS SECTION 

Z31J.1.1 1 So 0 MEV ISoOX USA RoHAIGHT 

O: HYDROGEN PRODUCTIONO 


41 NIOBIUM 53 

122132 4o SO MEV ISoO MEV 20oOX 2 GER DoDARVAS JUL 

HoKUESTERS 

KFK 

0: RADIATION DAMAGE ESTIMATES. CALCULATION OF 

TRANSMISSION RATES AND RADIOACTIVE AFTERHEATo 

Z23032 ISoO MEV 1 SoOX 1 CCP IONOGOLOVIN KUR 

O: HELIUM ACCUMULATION CALCULATIONSo 

4l _ NTOBFUM"53 NEUTRON ~TOTAL ALPHA PRODUCTION CROSS SECTION 

Z-41-210 1 5o 0 MEV 1 So OX 2 USA RoHAIGHT 

0: HELIUM PRODUCTIONO 


42 MOLYBDENUM NEUTRCN DIFFERENTIAL ELASTIC CROSS SECTION 

222140 loOO MEV 1 So 0 MEV lOoOX OoDARVAS 

SoCIERJACKS 

JUL 

KFK 

DISTRIBUTIONS FOR ENERGY STEPS OF 10 TO 20 PERCENT 

WOULD SUFFICEo 

CONFIRMATION OF ANL DATA USEFULo 

RADIATION DAMAGE ESTIMATESo 

Z23050 3o 00 MEV 1 So 0 MEV lOoOX CCP IoNoGOLOVIN KUR 

0: NEUTRON TRANSMISSION CALCULATIONSo 

42 MOLYBDENUM NEUTRCN 

"iNiLAlTIc'cRois'sicTloN 

Z2202S 3o 00 MEV 14o0 MEV lOoOX 3 Ffi DoBRETON FAR 


42 - MOLYBDENUM - ~ NEUTSON ENERGY DIFFIRINTIAL INELASTIC CRoii SECTION 

2240S1 15o 0 MEV ISoOX 1 CCP IoNoGOLOVIN KUR 

O: NEUTRON CALCULATIONS FOR BLANKET AND SHIELDINGo 

STA TUS 1—'-- . STATUS 

ALD COLES* - AWRE/0-85/7 0. DATA FOR 10 LEVELS AND CONTINUUM lo5 TO 6 MEVo 

ANL SMITH* - ANL/NCM-7. DATA TC 4 MEV FOR EVEN ISOTOPESo 

KTY MC ELLISTREM* - WORK UNDERWAY FOR EVEN ISOTOPES TO 6 MEVo 

42**MOLYBDENUM " NEUTRCN . CAPTVRE CROIS IECTION 

224052 lOoO MEV ISoO MEV 1 So OX 1 CCF IoNoGOLOVIN KUR 

o: HEAVY ISOTOPE ACCUMULATION CALCULATIONSo 

STA TUS— 

STATUS 

ANL POENITZo - (1574), DATA TC 2o5 MEVo 

HAR COATES - MEASUREMENT PLANNEOo 

42 MOLYSDENUM NEUTRCN" TOTAL PHOTON PRODUCTION CROSS SECTION 

224053 25o 3 MV ISoO MEV 1SoOX 1 CCP IoNoGOLOVIN KUR 



42 MOLYBDENUM _ NEUTRON TOTALPHOTON PRODUCTIONCROSS SECTION (CONTINUED) 

ZA1315 80 00 M£v 15.0 MEV 15.OX 3 USA FoGoPEREY ORL 


42 MOLYIOENUM ~ " SEUTRCN N,2N 

JZZlkt 15.0 MEV 10.OX 2 GER D.DARVAS JUL 

SoCIERJACKS 

KFK 

a: COUNTING OF OUTGOING NEUTRONS TO DETERMINE 

NEUTRON MULTIPLICATION BY TRANSMISSION IS 

REQUIRED, SINCE ACTIVITY IS PRODUCED BY MO-92 

AND MO-lOO ONLYo 

O: CALCULATION OF NEUTRON MULTIPLICATION AND 

RADIATION DAMAGEo 

Z2&&5& ISoO MEV ISoOX 1 CCP IoNoGOLOVIN KUR 

Q: SECONDARY ENERGY SPECTRUM REQUIRED AT 14o 0 MEVo 

O: NEUTRON MULTIPLICATION CALCULATIONS. 

Z32SM 1 5.0 MEV 1 OoOX 3 FR OoBRETON FAR 


STA TUS 

STATUS 

KFK CIERJACKSo - ( 1S73) o PRESENT EVALUATIONS RELY ON NUCLEAR S'VSTEMAT ICS AND 14-MEV DATA FOR MO, 

MO—52 ANC MG-rlOOo PRESENT ACCURACY 20 TO 30 PERCENTo 

42 MOLYBDENUM _ NEUTRON N.P 

2£21S£ 1o 50 MEV ISoO MEV 20o0X 2 GER CoCARVAS JUL 

SoCIERJACKS 

KFK 

O : RADIATION DAMAGE ESTIMATES. CALCULATION OF 


12&&55 1 So 0 MEV ISoOX 1 CCP IoNoGOLOVIN KUR 

O: HYDROGEN ACCUMULATION CALCULATIONSo 



Z9211.1 14o 0 MEV lOoOX 2 GER FoWELLER KFK 

O: FOR RADIATION DAMAGE CALCULATIONSo 

NO DATA AVAILABLEo 


STA TUS——r — STATUS 

KFK CIERJACKSo - (1573)o 14-MEV DATA POINTS FOR MO-92.-94.-96.-97 AND FISSION-SPECTRUM-AVERAGEO 

DATA ONLYo PRESENT ACCURACY 30 TO 50 PERCENTo 

42 T MOLY55ENUM ' SEUTRCN S7ALPHA 

1221&S SoOO MEV ISoO MEV 20o0X 2 GER CoCARVAS JUL 

SoCIERJACKS 

KFK 

O: RADIATION DAMAGE ESTIMATES. CALCULATION OF 


Z2465.6 15o 0 MEV ISoOX 1 CCP IONOGOLOVIN KUR 

O: HELIUM ACCUMULATION CALCULATIONSo 

ZJ2A22 14.0 MEV lOoOX 3 FR DoBRETON FAR 


STATUS—1-. 

STATUS 

KFK CIERJACKSo - ,(.1573 I o 14-MEV OATA FOR MO-92.-98. -100 ANC FISS ION-SPECTR UM-AVERAGED DATA FOR MO 

ONLYo ESTIMATED ACCURACY 30 TO SO FERCENTo 

_____________ _______ _____________________= 

ZAL314 2Eo3 MV lo 00 MEV ISoOX 2 USA RoHAIGHT LRL 

0: PRODUCTION OF AG-110M REOUIREDo 

EVALUATION REQUESTEDo 


STATUS * STATUS 

NPG IIJIMA* ( 157 £ I 0 THERE ARE 37 DATA FCINTS BELOW 6 MEV. BUT A SYSTEMATIC DISCREPANCY IS OBSERVED 

BETWEEN WESTON'S DATA ANC KCNONOV S CAT Ao 

74~TUNGSTEN NEUTRON INECASTFE'CROSI'IECTION 

722033 3o00 MEV 14o 0 MEV lOoOX 3 FR OoBRETON FAR 



74 TUNGSTEN KEUTRCK N.2N 

2S2SM 14o 0 MEV lOoOX 3 FR DoBRETON FAR 


STATUS 

STATUS 

JUL OA I Mo - NF/A 242 317< 1S75 I. DATA AT 14o7 MEV FOR ENR IC H.ED ISOTOPESo 

74 TUNGSTEN - - - - - NEUTRON*" N, P 

22223S 14o 0 MEV lOoOX 3 FR Do BRETON FAR 


STA TUS 

STATUS 

JUL OAI Mo - NF/A 242 317(1574). CATA AT 14o7 MEV FOR ENRICHED ISOTOPESo 

74~TUNGSTEN *" NEUTRON S7ALPHA 


o: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo 

STA TUS — STATUS 

JUL OAIMo - NF/A 242 317(1974). DATA AT 14o7 MEV FOR ENRICHED ISOTOPESo 

________ NEUTRCN TOTAL~CROSS~SECTION " I I 

2.41.515 2Eo3 *V 15o 0 MEV 1 USA DoDUDZI AK LAS 

a: EVALUATION WITH UNCERTAINTY-FILES REOUIREDo 

o: UNCERTAINTY FILES NEEDED TO PERFORM CROSS-SECTION 


OEVICESo 

MI NEW REOUESTo 

82 LEAD NEUTRCN ABSORPTION CROSS SECTION 

2.41.21.6 ISoO MEV USA DoOUDZIAK LAS 

0: EVALUATION WITH UNCERTAINTY-FILES REOUIREDo 

0: UNCERTAINTY FILES NEEDED TO PERFORM CROSS-SECTION 


DEVlCESo 



224252 2=o3 MV ISoO MEV ISoOX 2 CCP IoNoGOLOVIN 

0: GAMMA RAY SPECTRA REOUIREDo 

0: GAMMA RAY HEATING AND SHIELDING CALCULATIONSo 

NEUTRCN 

Z242S2 1 So 0 MEV 1SoOX 2 CCP IONOGOLOVIN KUR 

ii LEAB 204 *" "" NiuTRCN ~ N,2N 

O: POSSIBLE USE AS NEUTRON MULTIPLIERo 

I41J12 1 So 0 MEV ISoOX 2 USA RoHAIGHT LRL 

0: EVALUATION REOUESTEOo 

0: PRODUCTION OF PB-203o 


STA TUS——I .-: STATUS 

WWA OECOWSKI4- - NF/A 204 121 (1973). DATA 13 TO 18 MEVo 

83~BTSMUTH"*209 " 

= """NEUTRON TOTAL~PHOTON PR0CUCTI0NCR0is~siETI0N ~ 

223259 2So 3 MV 1 So 0 MEV ISoOX 2 CCP IONOGOLOVIN KUR 

0: GAMMA RAY SPECTRA REQUIREOo 


83~IISMUTH - 209 SIUTRCN N75N ~ " " ~ 

224262 ISoO MEV ISoOX 2 CCP IoNoGOLOVIN KUR 

0: POSSIBLE USE AS NEUTRON MULTIPLIERo 

STATUS--— — — —STATUS 

BRC FREHAUT+ - CEA-R-4627 (1974). DATA FROM THRESHOLD TO 14 ME.Vo 

io'THORI.UMîll 

= ~ = = NEUTRON " 

= = N75N 

= = = 

=-=-== = » = 

224.061 ISoO MEV ISoOX 2 CCP leNoGOLOVIN KUR 

o: POSSIBLE USE AS NEUTRON MULTIPLIERo 

=== = = = == = = = = = ==== s = = as a== = ===sa = ssssa == === = = ==== ===se===== = = s= = s=== = = === = sss===a== issasssssssaesss as ssnsssa 

FUSION LIST PAGE I He 19

90 THORIUM 232 NEUTRON N,3N 

22&T6£ ISoO MEV 1SoOX 2 CCP IoNoGOLOVIN KUR 

O: POSSIBLE USE AS NEUTRON MULTIPLIER© 

92 URANILM 238 NEUTRON " N,2N 

Z23S62 1 So 0 MEV 1 SoOX CCP IoNoGOLOVIN KUR 


Z41J1J 1 So 0 MEV 

o: EVALUATION REOUESTEOo 

O: PRODUCTION OF U-237, 


ALD MATHER* - AWRE/0-72/72, DATA 7o0 TO 12 MEVo 

BNW WOLKENHA UER + - 73PARIS 1 39, REVIEW THRESHOLD TO 16 MEVo 

LRL UANDRUM+ - PR/C 8 1938(1973), DATA 14 TO IS MEVo 

DUB BELQV+ - IJP 47 232(19731, WORK AT 15 MEVo 

BRC FREHAUT+ - CEA-R-4627 (19741, WORK THRESHOLD TO 15 MEVo 

92 URANIUM 238 NEUTRON N, 3N 

ZiiSii 1 So 0 MEV ISoOX CCP Io No GOLOVIN KUR 


ZA1.22fl 15o 0 MEV 1 5 oOX USA J oDo LEE LRL 

0: EVALUATION REOUESTEDo 

0: PRODUCTION OF U-236o 


92 URANIUM 238 DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION 

ZA131S 1 4o 0 MEV 1 5o OX 

0: SPECTRA AT SEVERAL ANGLES REOUIREOo 




IV.i 

IV. 

Nuclear Safeguards and. Accountability 

IV. A. 

Introduction 

The Nuclear Data Request List for Safeguards Development 

Purposes has been thoroughly revised in both content and 

format since its previous publication as INDC(NDS)-50 

(March 1973). The changes are summarized in the following 

table: 

Japanese 

List 

FRG 

List 

US 

List 

USSR 

List 

Withdrawn 

Requests 

— 

26 38 17 

Continued or 

modified Requests 

- 7 12 22 

New Requests 59 9 19 2 

Date of Submission 

to NDS October 73 May 1974 January 75 July 1974 

The list contains 130 requests from four countries - 

the Federal Republic of Germany, Japan, the Soviet Union 

and the United States. The few requests from France and 

the United Kingdom which may be related to safeguards are 

included in the Fission-Reactor Request List.

IV.ii 

IV.B. 


* 

Used in Assigning Priorities to Nuclear Data Re,quests for 

Safeguards Purposes 

First Priority - (l) 

First priority shall be given to those requests for 

nuclear data that 

1. are necessary for the refinement of an existing 

technique in order to bring its accuracy to within 

acceptable limits for safeguards purposes, or 

2. are essential for the development of a new and promising 

technique for the nondestructive assay and 

control of nuclear material in amounts that are 

significant to the safeguards system. 

Second Priority - (2) 

Second priority shall be given to those requests for 


1. are essential for the use or interpretation of an 

existing or proposed technique for nondestructive 

assay and that are now obtained either by extrapolation 

or by an empirical method but for which 

experimental confirmation is desirable, or 

2. are necessary for the development of a technique 

for non-destructive assay that may reasonably be 

expected to be useful for safeguards purposes. 

* These priority criteria were recommended for use by the 

International Nuclear Data Committee (INDC).

IV.iii 

Third Priority - (3) 

Third priority shall be given to those requests for 


1. may be needed for the nondestructive assay of 

materials not now included in the safeguards system 

but that are likely to be in the future, or 

2. are necessary for the assessment or elimination of 

minor sources of error in the assay of nuclear 

material, or 

3. are needed for the exploration of new techniques 

for non-destructive assay for future applications, 

or 

4. may be needed for the development of new techniques 

for non-destructive assay for which the required 

technology does not now exist but which may reasonably 

be expected to in the future.

IV. iv 

IV.C. Index to Safeguards Request List 

TARGET 

PAGE 

4 BERYLLIUM 9 0 0 0 0 00 o 0 O 0 C 0 o 0 I Vo 

36 KRYPTON 65 0 O 0 0 o O o O O 0 0 0 0 IV = 1 

40 ZIRCONIUM 95 O O O O O 0 C O 0 O 0 0 I Vo 1 

44 RUTHENIUM 103 O O O O C 0 0 0 O 0 0 c 0 IVo 1 

44 RUTHENIUM 106 0 0 0 0 00 0 O 0 0 0 0 I Vo 1 

45 RHODIUM ICe 0 C 0 C 00 0 0 0 0 0 0 IVc 1 

51 ANTIMONY 125 0 0 0 0 O 0 0 O 0 0 00 

a IVo 2 

54 XENON 133 0 0 O 0 00 0 0 0 0 0 0 IVo 2 

55 CESIUM 133 0 O 0 0 00 o 0 O 0 O 00 

o IVo 2 

55 CESIUM 134 0 O 0 0 00 o O O 0 O 00 

o IVo 2 

55 CESIUM 137 0 0 C 0 00 o 0 0 0 0 0 0 IVo 3 

56 BARIUM 14C O 0 0 0 00 o 0 O 0 C 0 0 IVo 3 

57 LANTHANUM 14C 0 0 0 0 o O o 0 0 O 0 0 0 0 IVo 3 

58 CERIUM 144 0 0 0 0 o o 0 0 O 0 O 0 o 0 IVo 3 

59 PRASEODYMIUM 141 0 0 0 0 0 o 0 0 0 0 0 0 00 IVo 4 

59 PRASEODYMIUM 144 0 0 0 0 00 o 0 O 0 0 0 0 IVo 4 

6 0 NEODYMIUM 142 0 0 O 0 00 o 0 0 0 0 o o 0 IVc 4 

60 NEODYMIUM 143 0 0 0 0 00 o 0 O 0 O 0 o 0 IVo 4 

60 NEODYMIUM 1 44 0 0 C 0 00 0 O 0 0 0 c 0 IVc 5 

60 NEODYMIUM 1 45 0 0 0 0 o O o O O 0 O 0 o 0 IVo 5 

60 NEODYMIUM 146 0 0 0 0 C 0 0 O 0 0 00 

c IVc 5 

60 NEODYMIUM 147 0 O O 0 00 0 O 0 0 00 

c IVo 5 

60 NEODYMIUM 148 0 0 0 0 00 o 0 O 0 0 O 0 0 IVc 5 

60 NEODYMIUM 150 0 0 0 0 00 0 O 0 O 0 0 IVo 5 

62 SAMARIUM 152 O 0 0 0 0 o 0 0 O C 0 0 00 IVo 6 

62 SAMARIUM 153 0 O O 0 00 o 0 0 0 O 0 0 IVo 6 

63 EUROPIUM 153 0 O 0 0 00 o 0 O C 0 0 c o IVo 6 

63 EUROPIUM 1 54 0 O O 0 O 0 O 0 C 0 0 0 0 0 o IVo 6 

63 EUROPIUM 155 0 0 0 o o 0 o 0 O 0 0 0 o 0 IVo 7 

92 URANIUM 235 0 O 0 0 00 o 0 O C 0 0 0 IVo 7 

92 URANIUM 236 0 O 0 O 0 0 0 0 O 0 0 IVo 8 

92 URANIUM 2 3.8 0 O O 0 0 ooooo'oo o 0 o IVo 8 

93 NEPTUNIUM 237 0 0 O 0 o 0 o 0 0 0 0 0 o 0 0 IVo 9 

94 PLUTONIUM 238 0 0 0 0 O O 00 O C C 0 0 IVc 9 

94 PLUTONIUM 239 0 0 0 0 00 0 O 0 0 0 0 IVc 1 0 

94 PLUTONIUM 240 0 0 O 0 o 0 o O O O O O 0 o o IVo 1 2 

94 PLUTONIUM 241 ooooooooooooo 0 o IVo 1 3 

94 PLUTONIUM 242 ocooooooooooc 0 o IVc 14 

95 AMERICIUM 241 ooooooooooooo 00 IVo 15 

95 AMERICIUM 242 o o o 0 o O o 0 0 o o o o 03 IVo 1 6 

95 AMERICIUM 243 0 0 o o O O O 0 0 O 00 

o IVo 17 

95 AMERICIUM 244 O 0 0 0 0 O o 0 O C O 0 o o o IVo 17 

\

IV. D. 

DATA REQUEST LIST FOR NUCLEAR SAFEGUARDS DEVELOPMENT

4 BERYLLIUM 9 NEUTRCN N,P DELAYED NEUTRON YIELD 

2HIQQ2 14c 0 MEV lOoOX 2 USA Rc 8*. WALTON 

DELAYED NEUTRON YIELD FROM BE-9 PRODUCED BY BETA 

DECAY OF L 1-9 REACTION PRODUCT REQUIREDo 

BACKGROUND IN DELAYED NEUTRON ASSAYSc 

714037 14o 0 MEV 16o 0 MEV lOoOX 2 CCP VoKcMARKOV GAC 

O: DELAYED NEUTRON YIELD FROM BE-9 PRODUCED BY BETA 

DECAY OF L1-9 REACTION PRODUCT REQUIREOo 

0: ALLOWANCE FOR BACKGROUND IN DELAYED NEUTRON 

COUNT ING 

STATUS 

STATUS 

LAS ALBURGER - PR 132 328, DELAYED NEUTRCN YIELD FROM BE-9 DECAY PRODUCT AT 16c MEVc 

36 KRYPTON 85 SPONTANEOUS TOTAL GAMMA RAY YIELD 

722001 1 o 0X 1 JAF. NoSASAMOTO JAE 

Q: YIELD PER DISINTEGRATION OF 514 KEV GAMMA RAY 

REQuIREDc 

0: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE 

MEASUREMENT, 


STATUS 

STATUS 

PRESENT ACCURACY 2-3 PERCENTo 

ORL HOREN - ND/B 5 131(1971) 0 

ORL MARTIN+ - ND/A l(1970)o 

GEL DENECKE+ - NSE 28 305(1967)o 

40 ZIRCONIUM 95 NEUTRON CAPTURE CROSS SECTION 

704003 2 5o 3 MV 5o OX 3 CCP So AcSKVORTSOV KUR 

Oo Ac MILLER 

KUR 

STATUS 

SAC RIBON, - 73E0LCGNA 1 235, REVIEWo 

Q: ALSO WANTED FOR c C 6 EV INCIDENT NEUTRONS, 

0: FOR ASSAY OF U AND PU IN FUEL ELEMENTS FROM 

FISSION PRODUCT GAMMA RAD1ATIONO 

44 RUTHENIUM 103 SPONTANEOUS TOTAL GAMMA RAY YIELD 

222002 

NoSASAMOTO 

JAE 

Q: YIELDS PER DISINTEGRATION OF 497 AND 610 KEV 

GAMMA RAY REQUIRED, 


MEASJJREMENTo 


222003 

NoSASAMOTO 

JAE 

Q: YIELD PER DISENTEGRATION OF 557 KEV GAMMA RAY 

REQUIREDc 


MEASUREMENT, 


STA TUS 

ORL MARTIN+ - ND/A £ l(1970)o 

UPP PETTERSSON* - ZP 233 260(1970), 

44 RUTHENIUM 106 NEUTRON CAPTURE CROSS SECTION 

204006 2 5,3 MV SoA,SKVORTSOV 

0,A,MILLER 

KUR 

KUR 

Q : ALSO WANTED FOR ,06 EV INCIDENT NEUTRONS, 

o: FOR ASSAY OF U AND PU IN FUEL ELEMENTS FROM 

FISSION PRODUCT GAMMA RADIATION, 

45 RHODIUM 106 SPONTANEOUS TOTAL GAMMA RAY YIELD 

222004 1 o 0 X JAP NoSASAMOTO JAE 

YIELD PER DISINTEGRATION OF 512, 622. AND 1050 

KEV GAMMA RAYS REQUIREOo 

FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE 

MEASUREMENT, 

NEW REQUESTo 

222005 3o 0 X 1 JAP NoSASAMOTO JAE 

YIELD PER DISINTEGRATION OF 616. 874, 1128 AND 

1562 KEV GAMMA RAYS REQUIREDo 


MEASUREMENT, 

NEW REQUESTc 

SAFEGUARDS LIST PAGE IVc 1

51 ANTIMONY 125 SPONTANEOUS TOTAL GAMMA RAY YIELD 

222006 loOX 

No SASAMOTO 

JAE 

YIELO PER DISINTEGRATION OF 176. 381 . 42 8. 464. 

601. 607, 636 AND 672 KEV GAMMA RAYS REOUIREDo 


MEASUREMENTo 

NEW REQUESTo 

STATUS 

ORL MARTIN* - NC/A 8 1 (1970)o 

BUQ NAGPAL+ - CJP 48 2978(1970lo 

ALG MARSOL+ - CR (SERIES B) 272 61(1971), 

54 XENON 133 HALF LIFE 

222016 JAP HoOKASHITA 

0: 

JAE 

DIFFERENT VALUES ARE QUOTED IN THE LlTERATUREo 


MEASUREMENT 


222012 

loOX HoOKASHITA JAE 

0: FOR 2c23 DAY ISOMERc 

0: DIFFERENT VALUES ARE QUOTED IN THE LlTERATUREo 


MEASUREMENTo 


STATUS 

ORL EMERY+ - NSE 48 31911972), 

MCM MACNAMARA+ - PR 78 129(1950lo 

HAR LARGE* - ND/A 7 477(1970) 0 

54 XENON 133 NEUTRON CAPTURE CROSS SECTION 

22801S 2 5o 3 MV 14o 0 MEV F HoOKASHITA JAE 

o: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE 

MEASUREMENTo 


222020 25o3 MV 25o 0 X HoOKASHITA JAE 

STATUS 

MCM KENNETT+ - JIN 5 253(1958), THERMAL VALUEo 

SAC RIBONo - 73BOLCGNA 1 235, EVALUATION FOR THERMAL AND FISSION SPECTRAc 

0: FOR 2c 23 DAY ISOMERc 

O: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE 

MEASUREMENTo 



204002 2So 3 MV 3o OX SoAcSKVORTSOV 

OoAo MILLER 

0: 

o: 

KUR 

KUR 

ALSO WANTED FOR o06 EV INCIDENT NEUTRONSo 

FOR ASSAY OF U AND PU IN FUEL ELEMENTS FROM 

FISSION PRODUCT GAMMA RADIATIONo 

222021 

2So 3 MV 1 4o 0 MEV 3oOX HoOKASHITA JAE 


O: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE 

MEASUREMENTo 


STATUS- 

SAC 

BOR 

KFK 

WUR 

NPG 

RIBONo - 7 2BOLCGNA 1 235. REVIEW.THERMAL TO 30 KEV ALSO FISSION NEUTRON SPECTRUM AVERAGEo 

RIGAUD+ - NP/A 176 545(1671 ). AT 14o0 MEVo 

KOMPE - NP/A 133 513(1969). FROM 10 KEV TO 150 KEV 

WI ODER - PRECISE DATA FROM OoOl TO 45 EV. TO BE PUBLISHED IN NSEo 

I IJIMA* (1575)o MANY EXPERIMENTAL DATA BELOW 15 MEV. BUT SYSTEMATIC DISCREPANCIES ARE 

OBSERVED ABOVE .10 KEVo 

55 CESIUM 134 SPONTANEOUS TOTAL GAMMA RAY YIELO 

222flfl2 loOX HoOKASHITA JAE 

YIELD PER DISINTEGRATION OF 563. 569. 796. AN 

802 KEV GAMMA RAYS REOUIREDo 


MEASUREMENTo 

NEW REQUESTo 

Z22B06 3o 0 X HoOKASHITA JAE 

YIELD PER DISINTEGRATION OF 1039. 1168, AND 1365 

KEV GAMMA RAYS REQUIREDo 

FOR BURN UP CALCULATION FROM NON-OESTRUCTIVE 

MEASUREMENTo 

NEW REQUESTo 

SAFEGUARDS LIST PAGE IVo 2

55 CESIUM 134 SPONTANEOUS TOTAL GAMMA RAY YIELD (CONTINUED) 

STATUS— 

-STATUS 

AE FORSYTH+ - 70 KARLSRUHE VOLol Po 521, 

I AEAo 

MHG RAESIDE + - NP/A 58 54(1967 >c 

PTN ABDUL-MALEK* - NP/A 106 225(1968)o 

THD HOFMANN+ - ZP 230 37(1970)o 

55 CESIUM 134 NEUTRCN CAPTURE CROSS SECTION 

204006 2Eo3 MV SoA:SKVORTSOV 

OoAoMILLER 

KUR 

KUR 

O: ALSO WANTED FOR o06 EV INCIDENT NEUTRONSo 

O: FOR ASSAY OF u AND PU IN FUEL ELEMENTS FROM 


222025 2 So 3 MV 3oOX 1 JAP He OKASHITA JAE 

O: RESONANCE INTEGRAL ALSO WANTEDo 


MEASUREMENT, 


STATUS 

STATUS 

SAC RIBONo - 7 3BOLCGNA 1 235. REVIEWo 


254513 2 Eo 3 MV lOoOX So AcSKVORTSOV 

0 oAc MILLER 

KUR 

KUR 

O: ALSO WANTED FOR c06 EV INCIDENT NEUTRONSo 

O: FOR ASSAY OF U AND PU IN FUEL ELEMENTS FROM 


56 BARIUM 140 CAPTURE CROSS SECTION 

204015 2Eo 3 MV SoOX 3 CCP So Ao SKVORTSOV KUR 

OoAoMILLER 

KUR 

0: ALSO WANTED FOR o06 EV INCIOENT NEUTRONSo 

0: FOR ASSAY OF U AND PU IN FUEL ELEMENTS FROM 


STATUS 

STATUS 

SAC RIBONo - 73B0LCGNA 1 235, REVIEWo 

57 LANTHANUM 140 SPONTANEOUS TOTAL GAMMA RAY YIELD 

254016 

1 oOX So AcSKVORTSOV 

0 o A; M ILLER 

KUR 

KUR 

YIELD OF GAMMA QUANTA PER BETA DECAY EVENT W 

FOR 328o 8 AND 81 5o 8 KEV GAMMA So 

FOR ASSAY OF U AND PU IN FUEL ELEMENTS FROM 


222009 

JAP N:SASAMOTO JAE 

0: YIELD PER DISINTEGRATION OF 328o 8. 487o 0. B15o8, 

AND 2522o 0 KEV GAMMA RAYS REQUIRED, 

0: FOR BURN UP CALCULATION FROM NON-OESTRUCT1VE 

MEASUREMENTo 


222010 NcSASAMOTO JAE 

a: YIELD PER DISINTEGRATION OF 432o 6 KEV GAMMA RAY 

REOUIREDo 


MEASUREMENTo 


STATUS- 

-STATUS 

CCP 

RUM 

CCP 

ORL 

GRE 

GUSEV - PROTECTION AGAINST GAMMA RADIATION FROM FISSION PRODUCTS. ATOM IZDA T, MOSCOW (19681c 

ARDISSON+ - RRF 16 1045(157l)o 

KALINNIKOV* - IZV 34 916(1970)o 

MARTIN* - ND/A 1(1970>o 

BLACHOT+ - CEA-N-1526(1972)o 

58 CER IUM 144 SPONTANEOUS 

S========S3BSSSSE=S==S3=C=a===S=B3 

TOTAL GAMMA RAY YIELD 

25451$ leO* SoAoSKVORTSOV 

OoAoMILLER 

KUR 

KUR 

O: YIELD OF GAMMA QUANTA PER BETA DECAY EVENT WANTED 

FOR 133o5 KEV GAMMAo 

O: FOR ASSAY OF U AND PU IN FUEL ELEMENTS FROM 


222511 HoOKASHITA JAE 

0: YIELD PER DISINTEGRATION OF 133c5 KEV GAMMA RAY 

REOUIREDo 


MEASUREMENTo 



51 ANTIMONY 125 SPONTANEOUS TOTAL GAMMA RAY YIELD (CONTINUED) 

STATUS 

STATUS 

CCP GUSEV PROTECTION AGAINST GAMMA RADIATION FROM FISSION PRODUCTS, ATOMIZDAT. MOSCOW (19681c 

SRE HILLER - KT 12 4e5(I97C)o 

DEB BERENYI - 73 PARIS VOLol Po269o 

MGT POTNIS+ - JPJ 29 539(1970)c 

HLS ANTTILA+ - ZP 237 126(1970lo 

ORL MARTIN* - ND/A 8 l(1970)o 

DEB BERENYI - 73 PARIS 1 269o 

GRE BLACHOTt - CEA-N-1526(1972)o 

CURRENTLY KNOWN TO ABOUT 5 PERCENTc 

59 PRASEODYMIUM 141 NEUTRCN CAPTURE CROSS SECTION 

722023 25=3 MV 

1 4o 0 MEV HoOKASHITA JAE 


0: FOR BURN UP CALCULATION FROM DESTRUCTIVE 

MEASUREMENT-, 


STATUS- 

-STATUS 

DEB 

DEB 

ANL 

ORL 

CSIKAI + - NF/A 95 229

60 NEODYMIUM 144 NEUTRCN CAPTURE CROSS SECTION 

Z22026 2 Eo 3 MV 3o 0 % 1 JAP HoOKASHITA JAE 

0: FOR BURN UP CALCULATION FROM DESTRUCTIVE 

MEASUREMENTo 

M: NEK REOUESTc 

STATUS 

ST AT US 

DEB CSIKAI+ - NF/A 55 229


Z22036 2 5o 3 MV 

1 4o 0 MEV YoNAITO JAE 



MEASUREMENT, 


OEB 

MUA 

ORL 

HAR 

PETOt - JNE 21 757(1967). AT 3o0 MEV RELATIVE TO GOLD CAPTURE, 15 PERCENT ERRORo 

C HAUBY+ - PR 152 1055(1966), AT 24o KEV RELATIVE TO INDIUM CAPTURE. 10 PERCENT ERRORo 

MACKLIN - NAT 157 370(1963). AT 30 KEV TO 17 PERCENTo 

CABELL - J IN 24 749(1562). THERMAL VALUEo 

62 SAMARIUM 153 NEUTRON CAPTURE CROSS SECTION 

72203.7 14c 0 MEV 25o0X P HoOKASHITA JAE 


MEASUREMENTo 


63 EUROPIUM 153 NEUTRON CAPTURE CROSS SECTION 

722036 2 So 3 My 

STA TUS- 

STATUS- 

1 4o 0 MEV HoOKASHITA JAE 



MEASUREMENTo 

M: NEW.REOUESTo 

RPI 

LAS 

DUB 

WUR 

KNOX+ - USNDC-11 22011974). IN PROGRESS 20 EV TO 100 KEVo 

HARLOW+ - CBWASHINGTON PoB37(1968)o 25 EV TO 10KEV 

KONKSt - SNP 7 310(196B)o 1 EV TO 50 KEVo 

WI ODER - PRECISE DATA FROM OoOl TO 10 EV, TO BE PUBLISHED IN NSEc 

ERROR AT THERMAL 15 PERCENT, AT LEAST 8 PERCENT IN REST OF ENERGY RANGEo 

63 EUROPIUM 154 HALF LIFE 

Z2201e loOX 1 JAF HoOKASHITA JAE 

O: DIFFERENT VALUES ARE QUOTED IN THE LlTERATUREo 


MEASUREMENT, 


STATUS 

STATUS 

ANL KARRAKER - PR £7 901 (1952) 

ORL EMERY* - NSE 48 319(1972) 

63 EUROPIUM 154 SPONTANEOUS TOTAL GAMMA RAY YIELD 


YIELDS PER DISINTEGRATION OF 123. 248. 592, 723, 

757, 873. 996. 1CC5. AND 1274 KEV GAMMA RAYS 

REQUIREDc 

FOR BURN UP CALCULATION FROM NON-DE STRUCT IVE 

MEASUREMENTo 

NEW REQUESTo 

Z22Q14 HoOKASHITA JAE 

STATUS 

LRL MEYER - PR 170 1089( 1 968 )o 

ORL RIED1NGER* - PR/C 2 2358

51 ANTIMONY 125 SPONTANEOUS TOTAL GAMMA RAY YIELD 

Z22fl IS loOX N:SASAMOTO JAE 

STATUS 

SGA EDER* - 73 PARIS 1 233. EVALUATION© 

LRL MEYER* - NP/A 132 177119691© 

GRE FOIN* - JPR 28 861 (1967)© 

0: VIELO PER DISINTEGRATION OF 06c5 AND 10So3 KEV 

GAMMA RAYS REOUIREDo 


MEASUREMENTo 



20X030 SoOO MEV 1Ao 0 MEV SoOX 2 USA Ro Be WALTON LAS 

0: DATA DESIRED FOR EXTRAPOLATION TO 15 MEVo 

CALCULATIONS OF MODERATING ASSEMBLIES FOR U ASSAYo 

STATUS 

STATUS 

A I TUTTLEo - NSE 56 37(1975), REVIEW WITH RECOMMENCED VALUES, 

ANL COXo - ANL/NDM-5 (1974).REVIEWo 

HFA SHALEV* - NSE 51 52(1973). SPECTRUM AVERAGE© 

I AE MANERO* - REA 10 637( 1972). REVIEWc 

KFK FIEG - EANCC(E)-157 (1973). WORK IN PROGRESS© 

FEI TARASKO* - YF 17 1149(1973). IN PROGRESS© 

SOR AMIEL - 73B0LCGNA.REPo13o TO 15 MEVo 

LAS KRICK* - .NSE 47 311 (1972)© Oo 1 TO 6© 5 MEVo 

92 URANIUM 235 NEUTRON SPECTRUM OF PROMPT GAMMA RAYS EMITTED IN FISSION 

Z-340QA 25o 3 MV 14o 0 MEV 2 = 0 X 3 CCP S:SoKOVALENKO RI 

0: YIELD AND SPECTRA WANTED FOR 5 TO 15 MEV GAMMASo 

A: 10:0 KEV GAMMA RESOLUTION WANTEDo 

O: FOR ASSAY OF U IN FUEL ELEMENTS FROM PROMPT 

GAMMAS, 


92 URANIUM 235 NEUTRON DELAYED GAMMA SPECTRUM FROM FISSION PRODUCTS 

Z01029 2 5o3 MV USA Ro Be WALTON 

LAS 

a: FISSION PRODUCT GAMMA RAY ENERGIES FROM 0© 25 TO 

5 MEVo 

DELAY TIME FROM 1 MILLISECOND TO 12 HOURS© 

ASSOCIATE GAMMA RAYS WITH FISSION PRODUCTS IF 

POSSIBLE© 

A: GE(LI) RESOLUTION AT lo 2 MEV SHOULD BE 2C S KEV, 

O: NON-DESTRUCTIVE ASSAY OF U-235© 

STATUS- 

LAS 

LAS 

ORL 

BNL 

HAR 

WALTON* - PR 17E 1894(19691© 

FISHER* - PR/B 134 796(1964)© 

MAIENSCHEIN* - 58 GENEVA VOL©15 366o 

CHRIEN - HAS DATA FOR U-235 AND PU-239© 

LARGE* - 69 VIENNA Po637, SOME DATA FOR Uo 


20402i 25o 3 MV So As SKVORTSOV 

OoAcMILLER 

KUR 

KUR 

O: YIELDS OF ZR—95 AND RU-106 ARE REQUIRED© 

o: FOR ASSAY OF U IN SPENT FUEL ELEMENTS BY 

THE FISSION PRODUCT GAMMA RAYSc 

MI MODIFIED (PARTIALLY FULFILLED)o 


FISSION YIELD OF RU-106. XE-133, CS-137, CE-141. 

CE-144. ND—143. ND-144, ND-1AS, ND-146. NO-147, 

ND-148, AND ND-150o 

DATA WANTED FOR THERMAL NEUTRONS, FAST REACTOR 

NEUTRONS(80-800 KEV), FISSION SPECTRUM NEUTRONS 

AND HIGH ENERGY NEUTRONS(14-15 MEV)© 

FOR BURN UP CALCULATION FROM DESTRUCTIVE AND 

NON-DESTRUCTIVE CALCULATIONSo 

NEW REOUEST© 

Z22050 50e0X HoOKASHITA JAE 

FISSION YIELD OF CS-134, PR-142 AND EU-154 WANTEDo 

OATA WANTED FOR THERMAL NEUTRONS. FAST REACTOR 

NEUTR0NS(BO-BOO KEV), FISSION SPECTRUM NEUTRONS 

AND HIGH ENERGY NEUTRONS(14-15 MEV)o 



NEW REQUESTo 



GAMMA 

FISSICN PRODUCT MASS VI ELD SPECTRUM ( CONTINUED) 


0: FISSION YIELD OF SM-152, AND SM-153 WANTEDo 

DATA WANTED FOR THERMAL NEUTRONS. FAST REACTOR 

NEUTRONS(80-800 KEV). FISSION SPECTRUM NEUTRONS 

AND HIGH ENERGY NEUTRONS(1 A-15 ME V)o 

0: FOR BURN UP CALCULATION FROM DESTRUCTIVE AND 



STATUS- 

K UR 

MILLER* - SJA 27 281(1568)o 

-STATUS 

SRE 

CCP 

AE 

CCP 

S GA 

HAR 

GRE 

CRC 

GEV 

ANL 

HILLER - KT 12 465(19701 

GRECHUSHKINA - TABLES SHOWING THE COMPOSITION OF PROMPT FISSION PRODUCTS FROM U-235, U-238, AND 

PU—239 FISSICN, ATOM1ZDAT, MOSCOW(1964), 

FORSYTH* - 70 KARLSRUHE VCLol Po521, 

G USE V - PROTECTION AGAINST GAMMA RADIATION FROM FISSION PRODUCTS, ATOMIZDAT, MOSCOW( 1 968)c 

LAMMER* - 73 PARIS PAPER 13, EVALUATION 

CROUCH - 73 PARIS PAPER 94, EVALUATION, 

DEVILLERS+ - 73 PARIS PAPER 63, EVALUATION; 

WALKER - 73 PARIS PAPER 34, EVALUATION, 

MEEK + - NE00-12154, EVALUATION, 

GLENDENIN+ - WORK IN PROGRESSo 


722540 

1 4o 0 MEV YcNAITO JAE 

A: ACCURACY REQUIRED AT THERMAL IS 3 PERCENT, 10 

PERCENT ABOVE, 

0: FOR BURN UP CALCULATION OF A PU LOADED THERMAL 

REACTOR, 


-STATUS 

GA 

GEL 

S GA 

HAR 

SRL 

CARLSON+ - NP/A 141 577( 1970). DATA THERMAL TO 20 KEVc 

ROHR+ - EANCCI El-157 ( 1973). IN PROGRESS 5 EV TO 2 KEV.; 

EDER* - 73 PARIS PAPER 12, COMPILATION, 

CABELL* - AERE-R-6761(1971), THERMAL, 

BAUMANN+ - NSE 32 265(19681. 8 PERCENT AT THERMALo 

9 2 URANIUM 236 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION 

701032 3,00 MEV 10,OX Ro Bo WALTON 

Q: ALSO FOR 14 MEV, NEUTRONS, 

0: BACKGROUND CORRECTION IN U- 235 SPENT FUEL ASSAYo 

92 URANIUM 236 ENERGY SPECTRUM OF FISSION NEUTRONS 

201031 lOoOX USA Rc B;WALTON LAS 

0: ONE ENERGY ABOVE FISSION THRESHOLD, 

0: BACKGROUND CORRECTIONS IN U-235 SPENT FUEL ASSAYo 


201035 So 00 MEV 14o 0 MEV 

A Ro Be WALTON LAS 

o: DATA DESIRED FOR EXTRAPOLATION TO IS MEVo 

CALCULATIONS OF MODERATING ASSEMBLIES FOR U ASSAYo 

STATUS 

A 1 

HFA 

IAE 

LAS 

ANL 

ALD 

TUTTLEo - NSE 56 37(1975), REVIEW WITH RECOMMENCED VALUESc 

SHALEV+ - NSE 51 52(1973), FAST REACTOR SPECTRUMc 

MANERO+ - REA 10 637(1972), REVIEW Ool TO 15 MEV, 

EVANS* - USNOC-3 127(1972), REVISED DATA AT 3o1 AND IS MEV, 

COXo ANL/NDM-=(1974)o MEASUREMENT AND EVALUATION, 2 TO 15 MEV, 

MCTAGGART - EANDC(UK)-151(1973) , FAST REACTOR SPEC MEASUREMENT IN PROGRESS, 


222.052 1 o 0 X HoOKASHITA JAE 

FISSION YIELD OF RU-106. XE-133. SM-152, SM-153. 

CE 141, CE—144. ND-143, ND-144. ND-145, ND-146, 

NO—147. ND-148, ND-150 AND CS-137 WANTEOo 

DATA WANTED FOR FISSION SPECTRUM NEUTRONS AND 

HIGH ENERGY NEUTR0NS(14 - 15 MEVIo 


NON-DESTRUCTIVE MEASUREMENTo 

NEW REQUESTo 

SAFEGUARDS LIST PAGE IV o 8


GAMMA 

FISSICN PRODUCT MASS VI ELD SPECTRUM ( CONTINUED) 

2*2053 

STA TUS- 

GRE DEV1LLERS* - 75 PARIS PAPER 63, EVALUATION 

GEV MEEK* - NEDO-12154, EVALUATION, 

HoOKASHITA 

JAE 

FISSION YIELD OF CS-134, PR-142 AND EU-154 

WANTEDc 

DATA WANTED FOR FISSION SPECTRUM NEUTRONS AND 

HIGH ENERGY NEUTRONS*14 - 15 MEV), 


NON-DESTRUCTIVE MEASUREMENTo 

NEW REQUEST, 

-STATUS 

93 NEPTUNIUM 237 NEUTRCN CAPTURE CROSS SECTION 

232125 1,00 KEV P c MCGRATH KFK 

NEUTRON AND CAP T URF WIDTHS UP TO 1 KEV NEEDEDo 

ACCURACY 3 PERCENT NEEDED TO 1C EV, 1C PERCENT 

ABOVE, 

ACCURACY 5 PERCENT IN NEUTRON WIDTH AND 10 PERCENT 

IN CAPTURE WIDTH; 

FOR BURN UP CALCULATIONS, 

NEW REQUEST, 

222126 1,00 KEV 5,00 MEV 10,OX 2 GER Pc MCGRATH KFK 



STA TUS 

STATUS 

LRL NAGLE+ - 71 KNCXVILLE 259, DATA IOC KEV TO 3 MEVc 

GEL THEOBALD* - EANDC (E) -1 57 (1973), IN PROGRESS TO 300 EV, 

ANC SMITH* - IN-1162(1969), EVALUATION TO 15 MEV; 

93 NEPTUNIUM 237 NEUTRON N.2N 

232122 lOcO MEV lOoOX 2 GER P;MCGRATH KFK 

O: FOR BURN UP CALCULATION AND CONTAMINATION BY 

BU-236, 


STATUS 

STATUS 

ALD PERKIN+ JNE/AB 14 69(1961), DATA AT 19,5 MEV, 

93 NEPTUNIUM 237 NiuTRON FISSICN CROSS_SECTION 

202069 1o 00 KEV 200o KEV ICoOX 2 GER P,MCGRATH KFK 

0: FOR BURN UP CALCULATIONS, 

M: MODIFIED (PARTIALLY WITHDRAWN), 

STATUS 

STATUS 

KTO KOBAYASHI* - EANCC(J)-26 (1972), DATA 4,3 TO 4,8 MEV, 

LAS JIACOLETTI* - LA-4763 (1971). DATA 20 EV TO 7,7 MEVc 

GEL THEOBALD* - EANDC(E)-150 (1972), IN PROGRESS 1 EV TO 1 KEVo 

NBS BOWMAN* - WORK PLANNED 10 KEV TO 2 MEVo 

CCP GAVRILOV* - AE 28 362(1970), DATA TO 1 KEVo 

LAS BROWN* - NP/A 15C 609(1970), BOMB DATAo 

IAE BAK* - KNS 3 77(1571), EVALUATION TO 19 MEVo 

SAC PAYA+ - EANDC(E )-127U(1970)o TO 2 KEVo 

NDC SCHETT* - EANDC-95 (1974), COMPILATION OF EXPERIMENTAL DATA AVAILABLE AS O c JANUARY 1974o 

NBS BOWMAN* - MEASUREMENTS PLANNED FOR 1975, 

94 PLUTONIUM 238 HALF LIFE 

241146 0,1X 2 USA W o W;STROHM MND 

O: FOR ACCURATE CALORIMETRIC ASSAY OF PU, 


94 PLUTONIUM 238 SPONTANEOUS FISSION HALF LIFE 

291143 2 USA EoVcWEINSTOCK BNL 

A - . REQUESTED ACCURACY - 1 TO 2 PERCENT, 

0: TO REDUCE ERRORS IN THE ASSAY OF HIGH-BURNUP PUo 


241151 1o0 X 2 USA N,S,BEYER ANL 

A: ACCURACY 3-5 PERCENT USEFUL IN SHORT TERM, 

0: FOR CALCULATION OF THE EFFECTIVE PU-240 FOR 

SPONTANEOUS FISSION MEASUREMENTS. OF PU IN 

NUCLEAR MATERIALS SAFEGUARDS, 



94 PLUTONIUM 238 SPONTANEOUS NEUTRONS EMITTED PER FISSION (NU BAR) 

74.1-1*5 1 oO X 2 USA EoV WEINSTOCK BNL 

0: TO REDUCE ERRORS IN THE ASSAY OF HIGH-BURNUP PUo 


Z 4115.4 loOX 2 USA No SC BEYER ANL 



SPONTANEOUS FISSION MEASUREMENTS OF PU IN 

NUCLEAR MATERIALS SAFEGUARDSc 


94 PLUTONIUM 238 GAMMA TOTAL NEUTRON YIELD 

714544 1Oo 0 MEV ICoOX 2 CCF VcKcMARKOV GAC 

O: PHOTONUCLEAR ASSAY OF PUo 

94^PLUTONIUM 238 GAMMA FISSION CROSS SECTION 

214544 1Oo 0 MEV lOcOX 2 CCP VcKcMARKOV GAC 

O: FOR PHOTONUCLEAR ASSAY OF PUc 

94 PLUTONIUM 23 8 GAMMA FISSION PRODUCT MASS YIELD SPECTRUM 

214045 1Oo 0 MEV lOoOX 2 CCP VoKc MARKOV GAC 

o: PHOTONUCLEAR ASSAY OF PUc 


252566 2So 3 MV 1Oc 0 MEV lOoOX 2 GER Pc MCGRATH KFK 


STA TUS 

STATUS 

LAS SILBERT* - LA.-5024 (1972) , CATA 18 EV TO 200 KEVo 

KFK HINKELMANN - KFK-1186(1970). EVALUATION TO 10 MEVo 


262565 1o 00 MEV lOoO MEV lOoOX 2 GER PoMCGRATH KFK 


STATUS 

STATUS 

ALD MOAT - AWRE/O-13/72• DATA 17 EV TO 1 MEVo 

LAS SILBERT - LA-4674 (1971), CATA 18 EV TO 3 MEVo 

LAS DRAKE* - LA-4420(1970 ). DATA TO 2o 6 MEV 

94_PLUT0NIUM_239 HALF LIFE 

241142 0 c 2X 2 USA WoW:STROHM MND 

0: FOR ACCURATE CALORIMETR IC ASSAY 0= PUo 



222041 25o 3 MV 14o 0 MEV 1 JAP YcNAITO JAE 

A: ACCURACY REQUIRED AT THERMAL IS 3 PERCENT. 10 



REACTOR, 


STATUS 

STATUS 

FEI CHELNOKOV* - YFI-13 6(1972). DATA 200 EV TO 12 KEV; 

ORL GWIN* - NSE 45 25(1971). DATA THERMAL TO 30 KEVc 

ORL WESTON* - USNOC-3 149(1972). WORK IN PROGRESSo 

HAR SCHOMBERG* - 70HELSINKI 1 31 So 100 EV TO 30 KEVo 

94 PLUTONIUM 239 NEUTRON CAPTURE GAMMA RAY SPECTRUM 

201544 2 5o 3 MV 1 OOo EV 20o OX 3 USA Ro Eo WALTON LAS 

0: FOR GAMMA RAY ENERGIES ABOVE lo 2 MEVo 

A: GAMMA RESOLUTION OF 20 5 KEV AT lo2 MEVo 

0: DEVELOPMENT OF NEW PU ASSAY TECHNIQUEo 

241136 25o3 MV 20o0 X 2 USA Ro B:WALTON LAS 

0: ABSOLUTE SPECTRUM REOUIREDo 

0: FOR DEVELOPMENT OF NONDESTRUCTIVE ASSAY METHODSo 



94 PLUTONIUM 239 CAPTURE TO FISSION RATIO (ALPHA) 

Z22046 14o 0 MEV Y,NAITO JAE 

A: ACCURACY REQUIRED AT THERMAL IS I PERCENT, 5 

PERCENT ABOVE, 


REACTOR, 


STATUS- 

-STATUS 

FEI 

FE I 

KUR' 

DUB 

ORL 

KFK 

ORL 

ANL 

KAP 

CHELNOKOV* - YFI-13 6( 1972). DATA 20C EV TO 12 KEVc 

KONONOV* - AE 32 85(1972), DATA 10 KEV TO 1 MEVc 

VOROTNIK0V+ - 73KIEV A 42. DATA 3 TO 200 KEVc 

BOLOTSK11+ - 73 KIEV 4 49. DATA THERMAL TO 30 KEVo 

WEST0N+ - LSNDC-7 179(1973), IN PROGRESS THERMAL TO 20 KEVo 

BANDL* - EANDC(E)-l57 (1973). IN PROGRESS 8c1 TO 60 KEVc 

GWIN* - NCSAC-42 199(1971). THERMAL TO 400 KEVo 

KATO* - NSE 45,37(1971 ). FAST REACTOR SPECTRUM, 

EI LAND* - NSE 44 180( 1971 ), PILE SPECTRUMo 


722048 25o 3 MV OoSX 1 JAP YoNAITO JAE 

O: DATA WANTED FOR EPI-THERMAL NEUTRONS ALSOo 

o: FOR BURN UP CALCULATION OF A PU LOADED THERMAL 

REACTORc 


STATUS 

STATUS 

IAE MANERO+ - REA 10 637(1972). REVIEWc 

CCP VOLODIN+ - AE 33 901(1972). DATA TO lo6 MEVo 

BRC FREHAUT* - EANDC(c)-150(1972). IN PROGRESS 7 EV TO 40 KEVo 

LRL HOWE* - L'SNDC-7 105(1973). IN PROGRESS THERMAL TO 15 MEVo 

RPI REED* - USNDC-7 202(1973). IN PROGRESS THERMAL TO 100 EVc 

ORL WESTON* - PRXC 10 1402(1974), DATA FCR RESOLVED RESONANCES IN RANGE 10 TO 170 EVc- 


701042 3o 00 MEV 14o 0 MEV 1OoOX 2 USA R,Be WALTON LAS 

0: DATA DESIRED FOR EXTRAPOLATION TO 15 MEV, 

CALCULATIONS OF MODERATING ASSEMBLIES FOR PU 

ASSAY, 

STATUS 

AI TUTTLE, - NSE 56 37(1975), REVIEW WITH RECOMMENCED "vALUESc 

ANL COX, - ANL/NDM-5 (1974). MEASUREMENTS AND REVIEW. 2 TO 15 MEVo 

FEI TARASKO* - YF 17 1149(1973), IN THERMAL AND FISSION SPECTRUMo 

HFA SHALEV+ - NSE El 52(19731. THERMALo 

STATUS 

KFK F IEG - EANDC(E >-157(1973). AT 14 MEV. IN PROGRESS© 

LAS EVANS* - USNOC-3 127(1972). .0,1 TO 15 MEV, REVISED 

LAS KRICK* - NSE 47 311(1972), Ool TO 1,8 MEV, 

FEI MAKSJUTENKO* - YFI-10 27(1971), 18 TC 21 MEV, 

IAE MANERO+ - REA 10 637(1972), REVIEWo 

94 PLUTONIUM 239 NEUTRON SPECTRUM OF PROMPT GAMMA RAYS EMITTED IN FISSION 

734002 25,3 MV 14,0 MEV 2,0 X 3 CCP S, Sc KOVALENKO RI 

O: YIELD AND SPECTRA WANTED FOR 5 TO 15 MEV GAMMA So 

A: 1Oc 0 KEV GAMMA RESOLUTION WANTEDo 

O: FOR ASSAY OF PU IN FUEL ELEMENTS FROM PROMPT 

GAMMAS, 


94 PLUTONIUM 239 NEUTRON DELAYED GAMMA SPECTRUM FROM FISSION PRODUCTS 

74104 3 2So 3 MV RoBo WALTON LAS 

FISSION PRODUCT GAMMA RAY ENERGIES FROM Oo 25 TO 

5c MEV, 

DELAY TIME FROM 1 MILLISECOND TO 12 HOURSo 

ASSOCIATE GAMMA RAYS WITH FISSION PRODUCTS 

POSSIBLEc 

GE(LI) RESOLUTION AT 1,2 MEV SHOULD BE 2o 5 

ACCURACY FOR ABSOLUTE GAMMA RAY YIELDSo 

NON-DESTRUCTIVE ASSAY OF PU-239 

STATUS 

-STATUS 

LAS WALTON* - PR 178 1894(1969)o 

LAS FISHER* - PR/e 134 796 (I 964 )o 

ORL MAIENSCHEIN - 5B GENEVA VOLolS 366, 

BNL CHRIEN - HAS DATA FOR PU-239, 

SAFEGUARDS LIST PAGE IV, 11

94PLUT0NIUM 23S NEUTRON 

p I SSI ON PRODUCT MASS YIELD SPECTRUM 

ZC4320 25o3 MV 1o 0 X 1 CCP Sc Ac SKVORTSOV KU" 

Oo A:MILLER 

KUR 

a: YIELDS OF CS-133 AND CS-I37 WANTEDC 

o: FOR ASSAY 0= PU IN SPENT =UEL ELEMENTS BY 

THE FISSION PRODUCT GAMMA RAYSO 

Z04023 

Sc Ac SKVORTSOV 

Oo Ac MILLER 

KUP 

KUR 

o: YIELDS OF ZR-95* PU-106, BA-140 AND CE-14A 

ARE REQUIREDo 

0: FOR ASSAY 0= PU IN SPENT FUEL ELEMENTS BY 

THE FISSION PRODUCT GAMMA RAYSo 

Z22Q54 IcQX 1 JAP He OK ASH IT A JAE 

FISSION YIELDS OF RU-106. CS-137, CE-141. CE-144. 

ND-143. ND-144, ND-14 5* ND-146, ND-147, ND-148. 

AND ND-15C WANTED 


NEUTRONS(80-800 KEVI, FISSION SPECTRUM NEUTRONS 

AND HIGH ENERGY NEUTRONS(14-15 MEVlc 



NEW REQUESTc 

Z22Q55 lo OX HcOKASHITA JAE 

FISSION YIELDS OF XE-133. SM-152 AND SM-153 

WANTEDc 

DATA WANTED FDR THERMAL NEUTRONS. FAST REACTOR 

NEUTRONS ( 80-800 KEV), FISSION SPECTRUM NEUTRONS 

AND HIGH ENERGY NEUTRONS(14-15 MEVlo 


NON-DESTRUCTIVE CALCULATIONSc 

NEW REQUESTc 

Z22056 HcOKASHITA JAE 

FISSION YIELD OF CS-134, PR-142 AND EU-154 

WANTEDc 


NEUTRONSC80-800 KEV), FISSION SPECTRUM NEUTRONS 

AND HIGH ENERGY NEUTRONS(14-15 MEVlo 

=OR BURN UP CALCULATION FROM DESTRUCTIVE AND 


NEW REQUESTc 

STATUS- 

KUR 

MILLER+ - SJA 27 281 (1969 )o 

-STATUS 

A E 

SRE 

CCP 

FORSYTH* - 70 KARLSRUHE VCLc1 Pc521o 

HILLER - KT 12 485(1970)0 

GRECHUSHKINA - TABLES SHOWING THE COMPOSITION OF PROMPT FISSION PRODUCTS FROM U-235. U-238 AND 

PU-239 FISSION. ATOMIZDAT• MOSCOW(1964), 

CCP GUSEV - PROTECTION AGAINST GAMMA RADIATION FROM FISSION PRODUCTS, ATOM IZDA T, MOSCOW!1969)o 

CCP GRESHILOV* - PRODUCTS CF PROMPT FISSION OF y-235, U-238, AND PU-239 FROM 0 TO 1 HOUR, A TOMIZDAT, 

MOSCOW(1565)o 

SGA LAMMER+ - 73 PARIS PAPER 13, EVALUATION, 

HAR CROUCH - 72 PARIS PAPER 94. EVALUATICNo 

GRE DEVILLERS* - 72 PARIS PAPER 63, EVALUATIONc 

CRC WALKER - 72 PARIS PAPER 34. EVALUATICNo 

GEV MEEK* - NEDO-12154 » EVALUATION, 

ANL GLENOENIN* - (1574), WORK IN PROGRESSo 


74-1138 A W,W-STROHM MNO 

O: FOR ACCURATE CALORIMETRIC ASSAY OF PUo 


94 PLUTONIUM 240 FISSION HALF LIFE 

Z41144 A EoVoWEINSTOCK BNL 

0: TO REDUCE ERRORS IN THE ASSAY OF HIGH-BURNUP PUc 


Z4U52 1 oOX N o S 3 BEYER ANL 

A: ACCURACY 3-5 PERCENT USEFUL IN SHORT TERMo 

O: FOR CALCULATION OF THE EFFECTIVE PU-240 FOR 


NUCLEAR MATERIALS SAFEGUARDSo 


94 PLUTONIUM 240 SPONTANEOUS NEUTRONS EMITTED PER FISSION (NU BAR) 

Z-41155 loOX 2 USA NoScBEYER ANL 







94 PLUTCNIUM 240 NEUTRON CAPTURE GAMMA RAY SPECTRUM 

Z4113S 2 So 3 MV 20c 0 X 2 USA Ro E:WALTON LAS 

0: ABSOLUTE SPECTRA REOUIREOo 

0: FOR DEVELOPMENT OF NONDESTRUCTIVE ASSAY METHODo 



701045 750o KEV 14o 0 MEV 20o0X 2 USA Rc 6-. WALTON LAS 

0: DATA DESIRED FOR EXTRAPOLATION TO 15 MEVo 

CALCULATIONS OF MODERATING ASSEMBLIES FOR PU 

ASSAYc 

STATUS 

STATUS 

A I TUTTLEc - NSE S6 37(1975), REVIEW WITH RECOMMENCED VALUESc 

IAE MANERO+ - REA 10 637(1972). REVIEWo 

94 PLUTONIUM 240 MISC 

Z02D7S Oo 3X 2 GER VoSCHNEIDER ALK 

O: SPECIFIC DECAY HEAT IN WATTS/GRAM REOUIREDo 

PERCENTAGE OF HEAT CARRIED OFF BY LONG RANGE 

PARTICLES (X-RAYS, GAMMA RAYS) USEFULo 

0: FOR CALORIMETRIC PU DETERMINATION, 

STATUS 

STATUS 

THE DECAY HEAT IS DETERMI NEC BY 2 METHODS = 

1) FROM HALF-LIFE (6620 + - 50 YR) AND ALPHA ENERGY (5255o5 +- 0,7 KEV), ONE OBTAINS = 

7o 0088 +- Oo 0530 MILLIWATTS/GRAMMEo 

2) FROM CALORIMETRIC MEASUREMENT ONE OBTAINS = 7,1046 • - OcOlSO MILL IWATTS/GRAMMEc 

RESOLUTION OF DISCREPANCY (lo37 PERCENT) BETWEEN THE 2 METHODS (QUOTED UNCERTAINTIES 0o76 

PERCENT AND 0o21 PERCENT) DESIRABLE: 

CCP DOKUCHAEV - AE 6 74(1959) AND JNE/A 11 195(1960). HALF-LIFE GIVENo 

PAR LEANG - CR 255 3155( 1962), ALPHA ENERGY GIVENo 

DRF OETTINGo - ST I-XPUB/l 62 55 (1968), THERMODYNAMICS OF NUCLEAR MATERIALS, (PROCo SYMPo VIENNA. 1967) 

IAEA, VIENNA, 1968o CALOFIMETRIC MEASUREMENT OF DECAY HEAT AND HALF LIFEc 

KFK WE ITKAMP+ - 73PARIS 1 197, REVIEW OF DISCREPANCIES AND RE-EVALUATION OF GETTING 1 S DATAo 


Z4114S 1 o OX 2 USA WoW-.STROHM MNO 

0: FOR ACCURATE CALORIMETRIC ASSAY OF PUo 


94 PLUTONIUM 241 GAMMA TOTAL NEUTRON YIELD 

Z1404S 1Oo 0 MEV lOoOX 2 CCP VcKcMARKOV GAC 

0: FOR PHOTONUCLEAR ASSAY OF PUo 

94 PLUTONIUM 241 GAMMA FISSICN CROSS SECTION 

Z14047 1Oo 0 MEV lOcOX 2 CCP VoKcMARKOV GAC 

O: FOR PHOTONUCLEAR ASSAY OF PUo 

94 PLUTONIUM 241 GAMMA FISSICN PRODUCT MASS YIELD SPECTRUM 

Z14046 1Oo 0 MEV lOoOX 2 CCP VcKcMARKOV GAC 

o: FOR PHOTONUCLEAR ASSAY OF PUo 


722042 25o3 MV 1 4o 0 MEV Yc NAITO JAE 

STATUS 

ORL WEST0N+ - LSNDC-3 149(1972), WORK IN PROGRESS THERMAL TO 30 KEVc 

SOR CANER+ - IA-1276(1973), EVALUATION TO 15 MEV 




REACTORo 



741140 25o3 MV 20o OX 2 USA Ro Ec WALTON LAS 

Q: ABSOLUTE SPECTRA REQUlREDo 




94 PLUTONIUM 241 CAPTURE TO FISSION RATIO (ALPHA) 

222047 

14o 0 MEV YCNAITO JAE 

A: ACCURACY REQUIRED AT THERMAL IS 1 PERCENT. 5 


O: FOR BURN UP CALCULATION OF A PU LOADED THERMAL 

REACTOR, 


ORL WESTON+ - LSNDC-7 179(1973), IN PROGRESS THERMAL TO 200 KEVo 

-STATUS 

ANL OAVEY - 70HELSINKI 2 119o REVIEW , Ocl TO 10 MEV, 

KAP EI LAND* - NSE 44 180(1971), PILE SPECTRUM, 


201046 

14c 0 MEV lOcOX Ro Be WALTON LAS 

DATA DESIRED FOR EXTRAPOLATION TO IS MEVo 

CALCULATIONS OF MODERATING ASSEMBLIES FOR 

ASSAYo 

STATUS- 

STATUS- 

A I TUTTLEo - NSE S6 37(1975), REVIEW WITH RECOMMENCED VALUES, 

LAS KEEPIN - NUC 2C 150( 1962), CNLY AT THERMALo 

ANL . MEADOWSo (1974 lo WORK BEING PLANNEDc 

-STATUS 

94 PLUTONIUM 241 NEUTRON FISSION PRODUCT MASS YIELD SPECTRUM 

204021 

ScAcSKVORTSOV 

OoA,MILLER 

KUR 

KUR 

Q: YIELD OF RU-144 WANTEDo 

o: FOR ASSAY OF PU IN FUEL ELEMENTS BY MEANS 

3F FISSION PRODUCT GAMMA RADIATIONo 

M: SUBSTANTIAL MODIFICATION SO 

Z22052 

HoOKASHITA 

JAE 

FISSION YIELO OF CS-137 AND CE-144 WANTED: 


NEUT RON S(80-80C KEV). FISSION SPECTRUM NEUTRONS 

AND HIGH ENERGY NEUTRONS(14—15 MEV)o 


NON-DESTRUCTIVE CALCULATIONSo . 

NEW REQUESTo 

722056 1 o 0 X HcOKASHITA JAE 

FISSION YIELD OF XE-133, CE-141, ND-143. NO-144, 

ND-145, ND-146. ND-147, ND-148. ND-150, SM-152, 

SM-153 AND RU-106 WANTEOo 


NEUTRONS(80-800 KEV). FISSION SPECTRUM NEUTRONS 

AND HIGH ENERGY NEUTRONS(14-15 MEV)0 



NEW REQUEST, 

222059 SOo OX 2 JAP HoOKASHITA JAE 

0: FISSION YIELD OF CS-134, PR-142, AND EU-154 

WANTED, 


NEUTRONS(80-800 KEV), FISSION SPECTRUM NEUTRONS 

AND HIGH ENERGY NEUTRONS( 1 4-1 5 MEV)o 

o: FOR BURN UP CALCULATION FROM DESTRUCTIVE AND 



STATUS 

STATUS 

HAR CROUCH - 73 PARIS PAPER 94, THERMAL EVALUATION 

CRC WALKER - 73 PARIS PAPER 34, THERMAL EVALUATION 

GEV MEEK* - NEDO-12154, THERMAL EVALUATIONo 

94 PLUTONIUM 241 MISC 

202023 VoSCHNEIDER ALK 

STATUS 

DRF GETTING - PR 168 1388. MEASUREMENT TO 5o0 PERCENT, 

o: 

SPECIFIC DECAY HEAT IN WATTS/GRAM REQUIREDo 

PERCENTAGE OF HEAT CARRIED OFF BY LONG RANGE 

PARTICLES (X-RAYS,GAMMA RAYS) USEFULo 

FOR CALORIMETRIC PU DETERMINATION, 

94 PLUTONIUM 242 FISSICN HALF LIFE 

241153 loOX 2 USA NoSc BEYER ANL 


O: FOR CALCULATION OF THE EFFECTIVE PU-240 FOR 


NUCLEAR MATERIALS SAFEGUARDSo. 



94 PLUTONIUM 2 42 SPONTANEOUS NEUTRONS EMITTED PER FISSION (NU BAR) 

Z4U55 NoS;BEYER ANL 


O:- FOR CALCULATION OF THE EFFECTIVE PU-240 FOR 





722043 1 4o 0 MEV Yc NAITO JAE 


PERCENT ABOVEo 


REACTORo 


Z32128 1 Oo PoMCGRATH KFK 

STATUS- 

A: ACCURACY 3 PERCENT FOR THERMAL AND 10 PERCENT 

ABOVE THERMALc 

0: FOR BURN UP CALCULATION AND PRODUCTION OF 

C M— I SOT OPE So 


GEL 

RPI 

ORL 

SOR 

MTR 

CRC 

POOR TMAN St - NF/A 207 342( 1973), DATA 2 EV TO lc3 KEV-. 

SANISLO* - USNDC-11 220(1974). KEV TIME-OF-FLIGHT DATA BEING ANALYZEDc 

WESTONc - (1974), DATA TC 2CC KEVc 

CANERt - I A-1275 (1973). EVALUATION TO 15 MEVo 

YOUNG* - IN-140 7 63(1970)o THERMAL VALUE 

DURHAM* - CJP 48 716(1970)c THERMAL VALUE 


Z41141 25o 3 MV 20o OX A RoBcWALTON LAS 

Q: ABSOLUTE SPECTRA REQUIREOo 




722125 25o 3 MV 1 Oo 0 MEV PoMCGRATH KFK 

A: ACCURACY 3 PERCENT FOR THERMAL AND 10 PERCENT 

ABOVE THERMALc 

O: FOR BURN UP CALCULATIONSo 


94 PLUTONIUM 242 DELAYED NEUTRONS EMITTED PER FISSION 

Z01047 3o 00 MEV 20o0X 3 USA Rc Be WALTON LAS 

o: ALSO REQUIRED FOR 14 MEVo INCIDENT NEUTRONSo 

O: CALCULATIONS OF MODERATING ASSEMBLIES FOR PU 

ASSAYS) 

95 AMERICIUM 241 HALF LIFE 

Z41150 Oo 2X 2 USA WoWcSTROHM MND 

O: FOR ACCURATE CALORIMETRIC ASSAY OF PUo 


95 AMERICIUM 24T GAMMA TOTAL NEUTRON YIELD 

713052 1Oo 0 MEV lOoOX 2 CCF VoKcMARKOV GAC 

0: FOR PHOTONUCLEAR ASSAY OF PUo 

95 AMERICIUM 241 GAMMA FISSION CROSS SECTION 

714051 1Oo 0 MEV lOoOX 2 CCP VcKcMARKOV GAC 

0: FOR PHOTONUCLEAR ASSAY OF PUc 

STA TUS 

STATUS 

SAS KATZ + - 58 GENEVA VOLo15 P0I880 

CCP GANGRSKY* - SNF 11 54(1970)o 

95 AMERICIUM 241 GAMMA FISSION PRODUCT MASS YIELD SPECTRUM 

Z14Q50 1Oo 0 MEV lOoOX 2 CCP VoKcMARKOV GAC 

O: FOR PHOTONUCLEAR ASSAY OF PUc 


95 AMERICIUM 241 GAMMA FISSICN PRODUCT MASS VI ELD SPECTRUM ( CONTINUED) 

STATUS 

STATUS 

SAS KATZ+ - 56 GENEVA VOLo15 P0I880 

CCP GANGR SKY+ - SNF 11 54(1970)o 


762.061 2 5o 3 MV I Oo 0 MEV lOoOX GER PoMCGRATH KFK 



722544 25o 3 MV 1 4o 0 MEV JAP YoNAITO JAE 




REACTORo 


-STATUS 

BUC 

BUC 

FEI 

KFK 

CCP 

HAR 

ORL 

HAR 

FLER0V+ NF/A 102 443( 1967). DATA Co 3 TO 608 MEVo 

VILCOVc - SCF 22 795(1970). DATA AT 7 MEVo 

DOVBENKO+ - INCC(CCP)-9 7(1970). THERMALc 

HINKELMANN - KFK-1186( 1970 I . EVALUATION TO 10 MEVc 

I VANOVA + - AE 30 369(1971), CROSS SECTION FOR FAST REACTOR SPECTRUMc 

WILTSHIRE-!- AERE-R-7363 (1 973 ) . CROSS SECTION FOR FAST REACTOR SPECTRUMc 

WESTON* - LSNDC-7 179(1973), THERMAL TO 20 KEVc IN PROGRESSo 

COATESc (1974), MEASUREMENTS PLANNED, AWAITING SAMPLES; 

95 AMERICIUM 241 NEUTRON CAPTURE GAMMA RAY SPECTRUM 

741142 2 5c 3 MV A Ro B:WALTON LAS 

0: ABSOLUTE SPECTRA REQUIREDo 

O: FOR DEVELOPMENT OF NONDESTRUCTIVE ASSAY METHODo 


95 AMERICIUM 241 FISSION CROSS SECTION 

752060 20o 0 KEV 1 Oc 0 MEV PoMCGRATH 



ORL WESTON+ - LSNDC-7 179(1973). IN PROGRESS THERMAL TO 200 KEVc 

HAR LYNN - MEASUREMENT PLANNEDo 

CCP FOMUSHKIN+- SNP 10 529(1970). 440 KEV TO 3c6 MEVo 

FEI SHPAK+ - INDC(CCPI-8 6(1970). 8 KEV TO 3o3 MEVo 

KFK HINKELMANN - KFK-1186(1970), EVALUATION TO 10 MEVo 


722545 2So3 14c 0 MEV JAP YoNAITO JAE 




REACTORo 


752131. 2 So 3 1 OOo KEV 20 o 0 X GER PcMCGRATH KFK 

0: CROSS SECTION NEEDED FOR 152 YEAR 

O: FOR PRODUCTION OF CM-244c 


CRC HANNA+ - PR 81 693(1951 Io 

LRL STREET - PR 85 135(l952)c 

LRL BOWMAN* - PR 166 1219(1968). RESONANCE PARAMETERS TO 4 EVc 

JUL IHLE+ - JIN 34(6) 2427(1972), PILEo 

95 AMERICIUM 242 NEUTRON FISSICN CROSS SECTION 

722130 2 5o 3 1 OOo R PoMCGRATH KFK 

0: CROSS SECTION NEEDED FOR 152 YEAR ISOMERc 

0: FOR PRODUCTION OF CM-2440 


LRL BROWNE+ - NCSAC-42 135(1971), IN PROGRESS TO 14 MEVc 

LRL PERKINS* - NSE 32 131(1968). DATA FROM 0o4 EV TC 4o7 MEVc 



732132 25o3 MV lOoO MEV lOoOX 1 GER PoMCGRATH KFK 

O: FOR PRODUCTION OF CM-244o 


STA TUS 

STATUS 

ANC SIMPSON+ - ANCR-1060 (1972). DATA o 5 EV TO I KEVo 

JUL IHLE+ - JIN 34(6) 2427(1972). PILEo 

MTR BERRETH+ - 1N-14C7 66(1970). RESONANCE PARAMETERS TO 25 EVo 

BUC BOCA+ - NP/A 134 541(1969). DATA 0o3 TO 4 MEVo 

95 AMERICIUM 244 NEUTRON ~ CAPTURE CROSS SECTION 

222133 2 5o 3 MV 1Oo 0 MEV 1Oo OX 1 GEF PoMCGRATH KFK 

O: FOR NEUTRON SOURCE CALCULATIONSo 



APPENDICES

APPENDIX A 

LIST OF COUNTRY COOES 

ARG 

ARGENTINA 

ALL 

AUSTRALIA 

AUS 

AUSTRIA 

BAN BANGLA DESH 

BLG 

BELGIUM 

BUL 

BULGARIA 

BZL 

CAN 

BRAZIL 

CANADA 

CCP SOVIET UNION 

DDR GERMAN DEMOCRATIC REPUBLIC 

DEN 

DENMARK 

EUR COMMISSION OF THE EUROPEAN COMMUNITIES 

FR 

FRANCE 

GER FEDERAL REPUBLIC OF GERMANY 

H,UN 

HUNGARY 

IND 

INDIA 

I SL 

ISRAEL 

ITY 

ITALY 

JAP 

NED 

NOR 

JAPAN 

NETHERLANDS 

NORWAY 

POL 

POLAND 

RUM 

ROMANIA 

SAF REPUBLIC GF SOUTH AFRICA 

SF 

SUD 

ShT 

FINLAND 

SWEDEN 

SWITZERLAND 

TV K 

TURKEY 

UK UNITED KINGDOM 

UNO UNITED NATIONS ORGANIZATION 

USA UNITED STATES 

YUG 

YUGOSLAVIA 

ZZZ INTERNATIONAL ORGANIZATION

LIST OF LABORATORY CODES 

APPENDIX B 

page 1 

ABD US ARMY ABERDEEN RESEARCH AND DEVELo CENTo, ABERDEEN, MDo USA 

AE AKTIEBOLAGET ATOMENERGI, STUDSVIK SWD 

AEC UNITED STATES ATOMIC ENERGY COMMISSION, WASHINGTON, OC USA 

A I ATOMICS INTERNATIONAL, CANOGA PARK, CALIFORNIA USA 

ALD UK AWRE, ALDERMASTGN UK 

ALG ALGERIA ALG 

ALK ALKEM GMBH, LEOPOLDSHAFEN . GER 

ANC AEROJET NUCLEAR CORPo, IDAHO FALLS, IDAHO USA 

ANL ARGONNE NATIONAL LABORATORY, LEMONT, ILLINOIS USA 

ARL AEROSPACE RESoLABS, WRIGHT-PATTERSON AIR-FORCE BASE, OHIO USA 

ATI ATOMINSTo DER 0ESTERREICHISCHEN HOCHSCHULEN, VIENNA AUS 

AUA AUSTRALIAN AEC RESEARCH ESTABLISHMENT, LUCAS HEIGHTS AUL 

AUB AUBURN UNIVERSITY, ALABAMA USA 

AUW ANORAH Uo. NUCLEAR RESEARCH LABo, WALTAIR IND 

BAC BULGARIAN ACADEMY OF SCIENCES, SOFIA BUL 

BET WESTINGHOUSE, BETTIS ATOMIC POWER LABo. PITTSBURGH, PAo USA 

BIR UNIVERSITY OF BIRMINGHAM, ENGLAND UK 

BNL BROOKHAVEN NATIONAL LABORATORY, UPTON, NEW YORK USA 

BN to BATTELLE NORTHWEST LABORATORY, RICHLAND. WASHINGTON USA 

BOL COMISION NACIONAL DE ENERGIA ATOMICA, BOLOGNA ITY 

BOF BORDEAUX UNIVERSITY FR 

BRC CEN BRUYERE LE CHATEL FR 

BRK UNIVERSITY OF CALIFORNIA, LAWRENCE BERKELEY LABo BERKELEY USA 

BUC INSTITUTE FOR ATOMIC PHYSICS, BUCHAREST RUM 

BUG BISHOP'S UNIVERSITY, QUEBEC CAN 

CAD CADARACHE, BOUCHES-DU-RHONE FR 

CAS CENTRO DI STUDI NUCLEARI DELLA CASACCIA, ROME ITY 

CCP SOVIET UNION CCP 

CNA CEKMECE NUCLEAR RESEARCH CENTER, ISTANBUL TUK 

COL COLUMBIA UNIVERSITY. NEW YORK CITY, NEW YORK USA 

CRC CHALK RIVER NUCLEAR LABORATORIES. ONTARIO CAN 

CSE CASE INSTITUTE OF TECHNOLOGY, CLEVELAND, OHIO USA 

DEB ATOMMAG KUTATO INTEZET, DEERECEN HUN 

DKE DUKE UNIVERSITY, DURHAM, NORTH CAROLINA USA 

DRF DOW CHEMICAL COMPANY, ROCKY FLATS, COLORADO USA 

DUB JOINT INSTITUTE FOR NUCLEAR RESEARCH, DUBNA ZZZ 

FAR CEA FONTENAY-AUX-ROSES, SEINE FR 

FE FUJI ELECTRIC JAP 

FEI FIZIKO-ENERGETICHESKIJ INSTITUT, OBNINSK CCP 

FOA RESEARCH INSTITUTE OF NATIONAL DEFENSE, STOCKHOLM SWO 

FRK Jo Wo GOETHE UNIVERSITY, FRANKFURT GER 

GA GENERAL ATOMIC, SAN DIEGO, CALIFORNIA USA 

GAC INSTITUTE FOR GEO- AND ANALYTIC CHEMISTRY, MOSCOW CCP 

GEB GENERAL ELECTRIC, BRDO. SUNNYVALE, CALIFo USA 

GEL B0C0M0N0 EURATOM, GEEL EUR 

GE V GENERAL ELECTRIC COo, VALLECITOS. CALIFo USA 

GIT GEORGIA INSTITUTE OF TECHNOLOGY, ATLANTA, GEORGIA USA 

GLS UNIVERSITY OF GLASGOW, SCOTLAND UK 

GOE UNIVERSITY C-F GOETTINGEN GER 

GRE C£A AND UNIVERSITY, GRENOBLE FR 

GRT GULF RADIATION TECHNOLOGY, SAN DIEGO. CALIFORNIA USA 

HAM INSTITUT FUER EXPERIMENTALPHYSIK, HAMBURG GER 

HAR UK ATOMIC ENERGY RESEARCH ESTABLISHMENT. HARWELL UK 

HED HANFORD ENGINEERING DEVELOPMENT LABo. RICHLAND. WASHo USA 

HFA TEC HNI ON HAIFA I SL 

HLS UNIVERSITY CF HELSINKI SF 

HR V HARVARD UNIVERSITY. CAMBRIDGE, MASS USA 

IA E INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA UNO 

IEN INSTITUTO DE ENGENHARIA NUCLEAR, RIO DE JANEIRO BZL 

IF U INSTITUT FIZIKI AN UKRAINSKOI SSR, KIEV CCP

APPENDIX B 

page 2 LIST OF LABORATORY CODES 

I IT ILLINOIS INSTITUTE OF TECHNOLOGY, CHICAGO, ILLINOIS USA 

IJI INSTITUT JADEPNYKH ISSLEOOVANIJ, KIEV CCP 

IRK INSTITUT FUER RADIUMFORSCHUNG UND KERNPHYSIK, VIENNA AUS 

IRT INTELCOM RADIATION TECHNOLOGY, SAN DIEGO, CALIFo USA 

JAE JAPAN ATOMIC ENERGY RESEARCH INSTITUTE, TOKAI JAP 

JAF JAPAN JAP 

JUL KERNFORSCHUNGSANLAGE, JUELICH GER 

JYV JYVAESKYLAE UNIVERSITY SF 

KAP KNOLLS ATOMIC POWER LABORATORY, SCHENECTADY. NEW YORK USA 

KFK KERNFORSCHUNGSZENTRUM, KARLSRUHE GER 

KGU GOSUDARSTVENNYJ UNIVERSITY, KIEV CCP 

KIG GKSS, GEESTHACHT GER 

KIL UNIVERSITY OF KIEL GER 

KOS KOSSUTH UNIVERSITY, DEBRECEN HUN 

KTC KYOTO UNIVERSITY JAP 

KTY UNIVERSITY OF KENTUCKY, LEXINGTON, KENTUCKY USA 

KUR IoVo KURCHATOV ATOMIC ENERGY INSTo. MOSCOW CCP 

KYL KYUSHU UNIVERSITY, FUKUOKA JAP 

LAS LOS ALAMOS SCIENTIFIC LABORATORY, NEW MEXICO USA 

LOU UNIVERSITY CF LODZ, LODZ POL 

LRL LAWRENCE LIVERMORE LABORATORY, LIVERMORE, CALIFORNIA USA 

L TI LOWELL TECHNOLOGICAL INSTITUTE, LOWELL, MASSo USA 

MCM MCMASTER UNIVERSITY, HAMILTON, ONTARIO CAN 

MGT MICHIGAN TECHNOLOGICAL UNIVERSITY USA 

MHG UNIVERSITY OF MICHIGAN USA 

MIT MASSACHUSETTS INSTITUTE OF TECHNOLOGY, CAMBRIDGE, MASSo USA 

MND MOUND LABORATORY, MI AMISBURG, OHIO USA 

MOL CoEo No . MOL BLG 

MTR IDAHO NUCLEAR CORPo, IDAHO FALLS, IDAHO USA 

MUA MUSLIM UNIVERSITY, ALIGARH IND 

MUN TECHo HOCHSCHULE, MUENCHEN GER 

NBS NATIONAL BUREAU OF STANDARDS, WASHINGTON, DoCo USA 

NDC NEA NUCLEAR DATA COMPILATION CENTER, SACLAY, FRANCE ZZZ 

NEL Uo So ARMY NUCLEAR EFFECTS LABORATORY, ABERDEEN, MARYLAND USA 

NEV UNIVERSITY OF NEUCHATEL SWT 

NPG NIPPON ATOMIC POWER INDUSTRY GROUP JAP 

NPL NATIONAL PHYSICAL LABORATORY. TECDINGTON UK 

NRD Uo So NAVAL RADIOLOGICAL DEFENSE LABo, SAN FRANC I SCO USA 

NYC NEW YORK UNIVERSITY, NEW YORK CITY USA 

OHO OHIO UNIVERSITY, ATHENS, OHIO USA 

ORE UNIVERSITY OF OREGON, EUGENE, OREGON USA 

ORL CAK RIDGE NATIONAL LABORATORY, TENNESSEE USA 

OSL UNIVERSITY OF OSLO NOR 

PAD UNIVERSITY OF PADUA ITY 

PAR UNIVERSITY OF PARIS ( INCLo GRSAY) PARIS FR 

PEL AE BOARD, PELINDABA, PRETORIA SAF 

PNC POWER REACTOR AND NUCLEAR FUEL DEVo CORPo, TOKAI-MURA JAP 

PTN PRINCETCN UNIVERSITY, PRINCETON, NoJo USA 

RAM ATOMIC ENERGY CENTRE, RAMNA, DACCA BAN 

RCN REACTOR CENTRUM NEOERLAND, PETTEN NED 

REK REHOVOTH LABo, ISRAEL AECo ISL 

RI KHLOPIN RADIUM INSTITUTE, LENINGRAD CCP 

RI£ RISO, ROSKILDE DEN 

RL RICHLAND OPERATIONS OFFICE, RICHLAND, WASHINGTON USA 

ROE ROSSENDORF BEI DRESDEN DDR 

RPI RENNSELAER POLYTECHNIC INSTITUTE, TROY, NEW YORK USA 

RUM ROMANIA RUM 

SAC CoEoNo SACLAY, GIF-SUR-YVETTE FR 

SAE SUMITOMO ATOMIC ENERGY INDUSTRIES, LTDo. TOKYO JAP 

SAI SCIENTIFIC APPLICATIONS INCo, LA JOLLA, CALIFORNIA USA

LIST OF LABORATORY CODES 

APPENDIX B 

page 3 

SAS UNIVo OF SASKATCHEWAN. SASKATOON CAN 

SGA OESToSTUDIENGESoFoATOMENERGIE. VIENNA AUS 

SOR SOREQ RESEARCH CENTER. YAVNE ISL 

SRE SIEMENS REAKTORENTWICKLUNG. ERLANGEN GER 

SRL SAVANNAH RIVER LABORATORIES. AIKEN. SoCo USA 

SUN SOUTHERN UNIVERSITIES NUCLEAR INSTo. FAURE. CAPE PROVo SAF 

THD TECHo HOCHSCHULE. DARMSTADT GER 

TNC TEXAS NUCLEAR CORPORATION, AUSTIN, TEXAS USA 

TRM BHABHA ATOMIC RESEARCH CENTRE, TROMBAY IND 

TUD DRESDEN, TECHNICAL UNIVERSITY AT DRESDEN AND PIRNA DDR 

UK UNITED KINGDOM UK 

UKW WINDSCALE REACTOR DEVELOPMENT LAESo, UKAEA UK 

UMK UNION MINIERE DU HAUT KATANGA, BRUSSELS BLG 

UPF UNIVERSITY OF UPPSALA SWD 

USA UNITED STATES OF AMERICA USA 

USP UNIVERSITY CF SAO PAULO, SAO PAULO BZL 

VDN CENTRAL BUREAU DER V0D0E0N0, ARNHEM NED 

WIN UK ATOMIC ENERGY ESTABLISHMENT, WINFRITH UK 

WIS UNIVERSITY OF WISCONSON, MADISON, WISCONSON USA 

WMU WESTERN MICHIGAN UNIVERSITY USA 

WUR EIDGo INSTITUT FUER REAKTORFORSCHUNG, WUERENLINGEN SWT 

WWA WARSAW UNIVERSITY POL 

YAL YALE UNIVERSITY, NEW HAVEN, CONNECTICUT USA 

YOK RIKKYO UNIVERSITY, YOKOSUKA JAP

APPENDIX C 

LIST OF CONFERENCE REFERENCES Page 1 

55 GENEVA FIRST INTERNATIONAL CONFERENCE ON THE PEACEFUL USES 

OF ATOMIC ENERGY, GENEVA 1955 

56 GENEVA SECOND UN CONFERENCE ON THE PEACEFUL USES OF ATOMIC 

ENERGY, GENEVA 1958 

66 WASHINGTON SECOND CONFERENCE ON NEUTRON CROSS SECTIONS AND 

TECHNOLOGY, WASHINGTON 1968, (NBS-299) 

65 VIENNA SECOND IAEA SYMPOSIUM ON THE PHYSICS AND CHEMISTRY 

OF FISSION. VIENNA 1969, (ST I/PUB/234) 

70 ANL EANDC SYMPOSIUM ON NEUTRON STANDARDS AND FLUX 

NORMALIZATION, ARGONNE 1970. (CONF-701002> 

70 HELSINKI SECOND IAEA CONFERENCE ON NUCLEAR DATA FOR REACTORS, 

HELSINKI 1970, (STI/PUB/259) 

70 KARLSRUHE IAEA SYMPOSIUM ON PROGRESS IN SAFEGUARDS TECHNIQUES, 

KARLESRUHE 1970 . (STI/PUB/260) 

71 CANTERBY CONFERENCE ON CHEMICAL NUCLEAR-DATA MEASUREMENTS AND 

APPLICATIONS, CANTERBURY 1971 

71 KIEV ALL USSR NEUTRON PHYSICS CONFERENCE, KIEV 1971, 

(NE JTRONNAY A FIZIKA, KIEV 1972) 

71 KNOXVILLE THIRD CONFERENCE ON NEUTRON CROSS SECTIONS AND 

TECHNOLOGY, KNOXVILLE 1971. (CONF-710301> 

72 BUDAPEST CONFERENCE ON NUCLEAR STRUCTURE AND STUDY WITH 

NEUTRONS, BUDAPEST 197 2 

72 KIEV 22ND CONFERENCE ON NUCLEAR SPECTROSCOPY AND NUCLEAR 

STRUCTURE, KIEV 1972 

72 VIENNA IAEA PANEL ON NEUTRON STANDARD REFERENCE DATA. 

VIENNA 1972, CST I/PUB/371 ) 

73 BOLOGNA IAEA PANEL ON FISSION-PRODUCT NUCLEAR DATA, 

BOLOGNA 1973, (IAEA-1691 

73 KIEV CONFERENCE ON NEUTRON PHYSICS, KIEV 1973 

73 PARIS IAEA SYMPOSIUM ON APPLICATIONS OF NUCLEAR DATA IN 

SCIENCE AND TECHNOLOGY, PARIS 1973. 

(ST I/PUB/34 3) 

75 WASH CONFERENCE ON NUCLEAR CROSS SECTIONS AND TECHNOLOGY, 

WASHINGTON 1975

APPENDIX C 

page 2 LIST OF JOURNAL REFERENCES 

AC ANALYTICAL CHEMISTRY 

AE ATCMNAJA ENERGIJA 

AF ARKI V FOER FYS IK 

AKE 

ATCMKERNENERGIE 

ANE ANNALS OF NUCLEAR SCIENCE AND ENGINEERING 

ANS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY 

APA ACTA PHY SICA AUSTRIACA 

AUJ AUSTRALIAN JOURNAL OF PHYSICS 

BAP BULLETIN OF THE AMERICAN PHYSICAL SOCIETY 

CJP CANADIAN JOURNAL OF PHYSICS 

CR COMPTES RENDUS 

DA/B DISSERTATION ABSTRACTS INTERNATIONAL B 

HP HEALTH PHYSICS 

HPA HELVETICA PHYSICA ACTA 

IJP INDIAN JOURNAL OF PHYSICS 

IZV IZVESTIYA AKAOEMII NAUK SSSR 

JIN JOURNAL OF INORGANIC AND NUCLEAR CHEMISTRY 

JNE JOURNAL OF NUCLEAR ENERGY 

JPJ JOURNAL OF THE PHYSICAL SOCIETY OF JAPAN 

KNS JOURNAL OF THE KOREAN NUCLEAR SOCIETY 

KT 

KERNTECHNIK 

NAT 

NATURE 

NC/A NUOVO CIMENTC SECTION A 

NC/B NUOVO CIMENTO SECTION B 

ND/A NUCLEAR DATA TABLES 

ND/B NUCLEAR DATA SHEETS 

NIM NUCLEAR INSTRUMENTS AND METHODS 

NP/A NUCLEAR PHYSICS SECTION A 

NSE NUCLEAR SCIENCE AND ENGINEERING 

NUC 

NUCLEONICS 

PL/B PHYSICS LETTERS SECTION 8 

PR PHYSICAL REVIEW 

PR/B PHYSICAL REVIEW PART B 

PR/C PHYSICAL REVIEW PART C 

PRL PHYSICAL REVIEW LETTERS 

PS PHYSICA SCRIPTA 

RCA RADIOCHIMICA ACTA 

REA ATCMIC ENERGY REVIEW 

RRP REVUE ROMAINE DE PHYSIQUE 

SCF STUDI SI CERCETARI DE FIZICA 

SJA SOVIET ATOMIC ENERGY 

SNP SOVIET JOURNAL OF NUCLEAR PHYSICS 

YF YADERNAYA FIZIKA 

ZP ZIETSCHRIFT FUER PHYSIK

APPENDIX C 

LIST OF LABORATORY REPORTS page 

AAEC/PR- 

AD- 

AE- 

AE-FN- 

AERE-FR/NP- 

AERE-R- 

ANCR- 

ANL — 

ANL/NDM- 

AtoRE-O- 

BNL- 

CEA-N- 

CEA-R- 

COO- 

EANDC- 

EANDC(E)- 

EANDC(J)- 

EANDC(OR)- 

EANDC( UK) - 

GA- 

GULF- 

GULF-RT- 

IA- 

IAEA- 

I N- 

INOC(IAEf— 

INDC(CCP)— 

INDC(NOR ) - 

INDC(SAF)- 

INDCC SEC)- 

I NR- 

INTEL-RT- 

JAER1- 

JINR-P7- 

KAPL-M- 

KFK- 

LA- 

LADC- 

NCSAC - 

NEANtiC(E) - 

NEANDC(UK)- 

NEDO- 

ORNL- 

OFNL-TM- 

RCN— 

RPI — 

STI/PL'B- 

UCRL- 

LSNDC- 

WAPD-TM- 

WASH- 

YFI- 

YK- 

ZFK — 

AUSTRALIAN AEC PROGRESS REPORTS 

UcSo DEPARTMENT OF DEFENCE REPORTS 

AKTIEBOLAGET ATOMENERGI REPORTS 

AKTIEBOLAGET ATOMENERGI INTERNAL REPORTS 

AERE HARWELL REPORTS 

AERE HARWELL REPORTS 

AEROJET NUCLEAR CORPORATION REPORTS 

ARGONNE NATIONAL LABORATORY REPORTS 

ARGCNNE NATIONAL LABORATORY REPORTS 

AtoRE ALDERMASTON REPORTS 

BROOKHAVEN NATIONAL LABORATORY REPORTS 

CENTRE D'ETUDES NUCLEA IRES NOTES 

CENTRE D'ETUDES NUCLEAIRES REPORTS 

USAEC CHICAGO OPERATIONS OFFICE REPORTS 

EUROPEAN-AMERICAN NUCLEAR DATA COMMITTEE 

EUROPEAN-AMERICAN 




GENERAL ATOMICS REPORTS 

GULF RADIATION TECHNOLOGY 

GULF RADIATION TECHNOLOGY 

ISRAEL AEC REPORTS 

IAEA TECHNICAL REPORTS 

IDAHO NUCLEAR CORPORATION 

I NTERAIATI ONAL 

INTERNATIONAL 




NUCLEAR 





NUCLEAR DATA COMMITTEE 






CATA 



REPORTS 

REPORTS 

REPORTS 

COMMITTEE 

COMMITTEE 

COMMITTEE 

COMMITTEE 

COMM ITTEE 

REPORTS 

REPORTS 

REPORTS 

REPORTS 

REPORTS 

DOCUMENTS 

REPORTS 

REPORTS 

REPORTS 

REPORTS 

INSTo BADAN JAOR, SWIERK+WARSZAWA REPORTS 

INTELCOM RADIATION TECHNOLOGY REPORTS 

JAPANESE ATOMIC ENERGY RESEARCH INSTITUTE REPORTS 

JOINT INSTITUTE FOR NUCLEAR RESEARCH DUBNA REPORT 

KNOLLS ATOMIC POWER LABORATORY REPORTS 

KERNFORSCHUNGSZENTRUM KARLSRUHE REPORTS 

LOS ALAMOS SCIENTIFIC LABORATORY REPORTS 

LOS ALAMOS SCIENTIFIC LABORATORY REPORTS 

USAEC NUCLEAR CROSS SECTION ADVISORY COMMITTEE REPORTS 

NUCLEAR ENERGY AGENCY NUCLEAR DATA COMMITTEE REPORTS 

NUCLEAR ENERGY AGENCY NUCLEAR DATA COMMITTEE REPORTS 

GENERAL ELECTRIC, ATOMIC POWER EQUIPMENT DEPTo REPORTS 

OAK RIDGE NATIONAL LABORATORY REPORTS 

OAK RIDGE NATIONAL LABORATORY TECHNICAL MEMOS 

REACTOR CENTo NEDERLAND, PETTEN, REPORTS 

RENSSELAER POLYTECHNIC INSTITUTE REPORTS 

IAEA PUBLICATIONS 

LAWRENCE RADIATION LABORATORY REPORTS 

UNITED STATES NUCLEAR DATA COMMITTEE REPORTS 

BfcTTIS ATOMIC POWER LABORATORY TECHNICAL MEMOS 

USAEC WASHINGTON OFFICE REPORTS 

JADERNO-FIZICHESKIE ISSLEDOVAN IJA REPORTS 

JADERNYE KONSTANTY 

ZENTRALINSTITUT FUER KERNFORSCHUNG ROSSENDORF REPORTS

NAMES AND ADDRESSES OF REQUESTORS 

AGH1NA. LeOeBe 

DIRECTOR. DIVo DE REATORES 

INSTITUTO DE ENGENHARI A NUCLEAR 

CIDAOE UNIVERSITARIA 

11. HA 00 PUNDAO 

RIO DE JANEIRO-GB-ZC-32 

BRAZIL 

ALBERT. Do 

ZENTRALINSTITUT FUER KERNPHYSIK 

ROSSENDORF BEI DRESDEN 

POSTFACH 19 

DRESDEN-BAD WEISSER HIRSCH 

D0R-8051. GERMAN DEMo REPo 

APPENDIX D 

page 1 

CASWELL. Ro So 

RADIATION PHYSICS DIVISION 

NATIONAL BUREAU OF STANDARDS 

WASHINGTON, Co Co 20234 

Uo So Ao 

CHRIST0V, Vo 

INSTITUTE OF NUCLEAR RESEARCH 

AND NUCLEAR ENERGY 

BULGARIAN ACADEMY OF SCIENCES 

SOFIA 13. 

BULGARIA 

BARRE . Jo Ye 

DPRMA-SECPR-CENTRE 

D'ETUDES 

NUC LEA IRES DE CADARACHE. C 0EoAo 

BoPo NO 1 

F~13115 SAINT PAUL LEZ DURANCE 

FRANCE 

BENZt, Vo 

DIRECTOR. NUCLEAR DATA AND 

CALCULATIONS LABORATORY 

CENTRO DI CA-LCOLO DEL Co No Eo No 

VIA MAZZ1NI 2 

1—40130 BOLOGNA 

ITALY 

BEYER. No So 

ARGONNE NATIONAL LABORATORY 

S700 SOUTH CASS AVENUE 

ARGONNE, ILLINOIS 60 439 

Uo So Ao 

BHAT, Mr 

NATIONAL NEUTRON CROSS SECTION CENTER 

BROOKHAVEN NATIONAL LABORATORY 

VPTON. NEW YCRK 11973 

Uo So Ao 

BRETON. Do 

CENTRE D 'ETUDES NUCLEAI RES 

BoPo NOo 6 

F-922 60 FONTENAY AUX ROSES 

FRANCE 

BRUNNER, Jo 

PHYSIK —ABTEI LUNG 

EIOGo INSTITUT FUER REAKTCRFORSCHUNG 

CH— 530 3 kUERENLINGEN 

SWITZERLAND 

CIERJACKS. So 

INSTITUT FUER ANGEWANOTE KERNPHYSIK 

KERNFORSCHUNGSZENTRUM KARLSRUHE 

POSTFACH 364C 

D-75 KARLSRUHE 

FEDERAL REPUBLIC OF GERMANY 

CLIFFORD, CoEo 

OAK RIDGE NATIONAL LABORATORY 

Po Oo BOX X 

OAK RIDGE. TENNESSEE 37830 

Uo So Ao 

CSIKAI. Jo 

INSTITUTE OF EXPERIMENTAL PHYSICS 

KOSSUTH UNIVERSITY 

Po Oo BOX 105 

H— 4001 DEBRECEN 

HUNGARY 

DAHLBERG, RoHo 

GENERAL ATCMIC 

Po Oo BOX 61606 

SAN DIEGO. CALIFORNIA 92138 

Uo So A o 

DARVAS. Do 

INSTITUT FUER REAKTORENTWICKLUNG 

KERNFORSCHUNGSANLAGE JUELICH 

POSTFACH 365 

D-517 JUELICH 


DAVEY. We 

LOS ALAMCS SCIENTIFIC LABORATORY 


LOS ALAMCS. NEW MEXICO 87544 

Uo So Ao 

BUTLER. Jo 

REACTOR SHIELDING GROUP 

ATOMIC ENERGY ESTABLISHMENT 

WINFRITH, DORCHESTER. DORSET 

UNITED KINGOCM 

CAMPBELL. CoGo 

HEAD, FAST REACTOR PHYSICS DIVISION 

BUILDING Ao 32 



UNITED KINGDOM 

DELEEUW-GIERTS. GO 

CENTRE D'ETUDE DE L'ENERGIE NUCLEAIRE 

B-2400 MCL 

BELGIUM 

DE TROYER. Ao 

UNION MINI ERE DU HAUT KATANGA 

6, RUE MONTAGNE DU PARC 

BRUSSELS, BELGIUM

APPENDIX 

page 2 

C 

DEVILLERS, Co 

CENTRE D'ETUCES NUCLEAIRES DE SACLAY 

BcPo NO 2 

F— 91190 GIF SLR YVETTE 

FRANCE 

HA1GHT, Re 

LAWRENCE LIVERMORE LABORATORY 

PO OO BOX eoe 

LIVERMORE, CALIFORNIA 94550 

Uo So Ao 

DUDZIAK, Oo 

LOS ALAMOS SCIENTIFIC LABORATORY 



Uo So Ao 

HANCOX, R E 

ATOMIC ENERGY RESEARCH ESTABLISHMENT 

HARWELL. DIDCCT 

BERKS OX11 ORA 


EHRLICH. Ro 

MANAGER, ADVANCED DEVELOPMENT 

ACTIVITY 

KNOLLS ATOMIC POWER LABORATORY 


SCHENECTADY, NoYo 12301 

Uo So Ao 

HANNA, GoCo 

PHYSICS DIVISION 

CHALK RIVER NUCLEAR LABORATORIES 

ATOMIC ENERGY OF CANADA LIMITED 

CHALK RIVER, ONTARIO 

CANADA 

ERTEK . Co 

CEKMEOE NUCLEAR RESEARCH CENTER 

Po Ko lo HAV.A ALAN I. ISTANBUL 

TURKEY 

HANSEN, Go Eo 




Uo So Ao 

FABRY. Ao 

CENTRE D"ETUCE DE L'ENERGIE NUCLEAIRE 

B-2400 MOL 

BELGIUM 

GARG, Go Bo 

NUCLEAR PHYSICS DIVISION 

BHABHA ATOMIC RESEARCH CENTRE 

TROMBAY, BCWBAY 400 085 

INDIA 

GERWIN, Ho 

INSTITUT FUER REAKTORENTWICKLUNG 

KERNFORSCHUNGSANLAGE JUELICH GMBH 

POSTFACH 365 

D— 517 JUELICH 


HEMMI6, Po Be 

01 VISION OF REACTOR DEVELOPMENT 

AND TECHNOLOGY 

Uo So ATOMIC ENERGY COMMISSION 

WASHINGTON. Do C. 0 20545 

Uo So Ao 

HERMANS, Me Eo Ao 

CENTRAL EUREAU DER VoDoEoNo 

UTRECHTSE'tEsG 310 

ARNHEM 

NETHERLANOS 

HOE JERUP , CoFo 

REACTOR PHYSICS DEPARTMENT 

RESEARCH ESTABLISHMENT RISOE 

DK-4000 ROSKILDE 

DENMARK 

GOEL. Be 

INSTITUT FUER NEUTRONENPHYSIK 

UND REAKTORTECHNIK 

KERNFORSCHUNGSZENTRUM KARLESRUHE 

POSTFACH 3640 



HOPKINS. Go 

GENERAL ATOMIC 

POOO BOX ei 6>ce 

SAN DIEGO, CALIFORNIA 92138 

Uo So Ao 

GOLOVIN, Io No 

IoVo KURCHATOV INSTITUTE OF ATOMIC 

ENERGY 

MOSCOW 0-182 

Uo So So Ro 

HUTCHINS. Be 

GENERAL ELECTRIC COo BRDO 

310 DE GUIGNE DRIVE 

SUNNYVALE. CALIFORNIA 94086 

Uo So Ao 

HAEGGBLOM, Ho 

•SECTION FOR REACTOR PHYSICS 

AB ATOMENERGI 

S—611 00 STVJDSVIK 

SWEDEN 

1 1 J I M A , Se 

NIPPON ATOMIC POWER INDUSTRY GROUP 

SUEHIRO-CHO 

KAWASAKI-SHI, KANAGAWA-KEN 210 

JAPAN

APPENDIX D 

page 3 

IIJIMA, 

To 

JAPAN ATCMIC RESEARCH INSTITUTE 

TOKAI-MURA. NAGA-GUN 

IBARAKI-KEN 319-11 

JAPAN 

MAENE, No 

CENTRE D'ETUCE DE L•ENERGIE NUCLEAIRE 

8— 2400 MCL 

BELGIUM 

ISLAM, Me Mo 

ATOMIC ENERGY CENTRE 

Po Oo BOX 164 

RAMNA. DACCA 

BANGLA DESH 

MACKLIN. RoLe 


Po Oo BOX X 


Uo So Ao 

ISVAR, Ao 

CEKMECE NUCLEAR RESEARCH CENTER 

Po Ko to HAVA ALANI, ISTANBUL 

TURKEY 

MAERKL. 

SIEMENS PEAKTORENTWICKLUNG 

GUENTHER-SCHAROWSKY-STRASSE 2 

D— 652 ERLANGEN 2 


KANDA, Yo 

KYUSHYU UNIVERSITY 

FUKUOKA-SHI 612 

JAPAN 

KATSURAGI. So 

DIVISION OF REACTOR ENGINEERING 

JAPAN ATCMIC RESEARCH INSTITUTE 

TOKAI-MURA, NAGA-GUN 


JAPAN 

KAWAI, Mo 

NIPPON ATOMIC POWER INDUSTRY GROUP 

SUEHIRO-CHO 

KAWASAKI-SHI, KANAGAWA-KEN 210 

JAPAN 

KOVALENKO. So So 

RADIEVYJ INSTITUT VoGo KHLOPINA 

ULo RENTGENA 1 

LENINGRAD P-22 

Uo So So Ro 

KUECHLE. Mo 


UND REAKTOFTECHNIK 


POSTFACH 364C 



KUESTERS. Ho 

INSTITUT FUER ANGEWANDTE REACTORTECHNIK 


POSTFACH 364 C 



LEE. Jo Do 

LAWRENCE LIVERMORE LABORATORY 

PO OO BOX ece 

LIVERMORE, CALIFORNIA 94550 

Uo So Ao 

MA IENSCHE IN, FoCo 

DIRECTOR. NEUTRON PHYSICS DIVISION 


Po Oo BOX X 

OAK RIDGE, TENNESSEE 37830 

Uo So Ao 

MARKOV. Vo Ke 

INSTITUTE FOR GEO- AND ANALYTICAL 

CHEMISTRY 

MO SCOW 

Uo So So Ro 

MATSUNOBU. Ho 

TECHNICAL SECTION, TECHNICAL DEPARTMENT 

SUMITOMO ATOMIC ENERGY INDUSTRIES. LTDo 

2-6-1 KAJICHC. CHIYODAKU 

TOKYO 101 

JAPAN 

MC CROSSON. Fetie 

Eo Io OU FONT DE NEMOURS C COoINCo 

SAVANNAH RIVER LABORATORY 

Po Oo BOX 117 

AIKEN, SOUTH CAROLINA 29801 

Uo So A 0 

MC ELROY, Wo No 

HANFORD ENGINEERING DEVELOPMENT 

LABORATORY 

Po Oo BOX 157,0 

RICHLAND, WASHINGTON 99352 

Uo So Ao 

MC GRATH, Pe 

INSTITUT FUER ANGEWA NDTE KERNPHYSIK 


POSTFACH 364C 

D— 75 KARLSRUHE 


MC NALLY, JoRo 


Pe Oo BOX X 


Uo So Ao

APPENDIX D 

page 4 

MICHAUDON, Ao 

CENTRE D"ETUDES DE 

8RUYERES-LE-CHATEL 

BoPo NOo 61 

F-92120 MONTCOUGE 

FRANCE 

ORPHAN. Ve Jo 

SCIENTIFIC APPLICATIONS INCo 


1200 PROSPECT STREET 

LA JOLLA, CALIFORNIA 92037 

Uo So Ao 

MILLER. Oo Ae 

Io Vo KURCHATOV INSTITUTE OF ATOMIC 

ENERGY 

MOSCOW D-182 

Uo SoSoRo 

ORTON, Go To 

RICHLAND OPERATIONS OFFICE 

Po Oo BOX 550 

RICHLAND. WASHINGTON 99352 

Uo So Ao 

MOTZ. He To 

PHYSICS DIVISION LEADER 



LOS ALAMOS, NEW MEXICO 87544 

Uo So Ao 

PEREY. FoGe 


Po Oo BOX X 


Uo So Ao 

NAITO. Yo 

JAPAN ATOMIC RESEARCH INSTITUTE 



JAPAN 

PERRY. AoMo 


PoOo BOX X 


Uo So Ao 

NAKAMURA. Ho 

FUJI ELECTRONIC COMPANY 

1-1 TANAEE SHINDEN 

KAWASAKI-KU, KAWASAKI-SHI 

KANAGAWA-KEN 210 

JAPAN 

RIBON. Po 

SERVICE C€ LA METROLCGIE ET DE LA 

PHYSIQUE NEUTRON I QUES FONOAMENTALES 

CENTRE D.'ETUDES NUCLEAIRES DE SACLAY 

BoPo NO 2 

F—51190 GIF SUR YVETTE 

FRANCE 

NAVALKAR. M ePo 

NUCLEAR PHYSICS DIVISION 

BHABHA ATOMIC RESEARCH CENTRE 

TROMBAY, BOMBAY 400 085 

INDIA 

NEUTRON DOSIMETRY GROUP 

COMMISSION OF THE EUROPEAN 

COMMUNITIES 

Co BoNo Mo 

STEENWEG NAAR RETIE 

GEEL 

BELGIUM 

ROSE. Bo 

CHAIRMAN 

UNITED KINGDOM NUCLEAR DATA COMMITTEE 


HARWELL. DICCOT 

BERKS 0X11 OKA 


SASAMOTO, No 



IBARAKI — KEN 319-11 

JAPAN 

NIKOLAEV. Mo No 

INSTITUTE OF PHYSICS AND ENERGETICS 

OBNINSK, KALUGA REGION 

Uo So So Ro 

OHTA. Me 

KYUSHYU UNIVERSITY 

FUKUOKA — SHI 612 

JAPAN 

OKASHITA. Ho 



IBARAKI—KEN 315-11 

JAPAN 

SCHENTER, RoEo 

HANFORD ENGINEERING DEVELOPMENT 

LABORATORY 

PoOo BOX 1570 

RICHLAND. WASHINGTON 99352 

Uo SoAo 

SCHMIDT. Ae 

CENTRE D 'ETUDES NUCLEAI RES DE 

CADARACHE 

BoPo NO 1 

F-13115 SAINT PAUL LEZ DURANCE 

FRANCE

APPENDIX D 

page 5 

SCHNEIDER. Vo 

ALKEM—ALPHA—CHEMIE UND METALLURGIE GMBH 

75 CI LEOFOLDSHAFEN 


USACHEV. LoNo 

INSTITUTE FOR PHYSICS AND ENERGETICS 

OBNINSK. KALUGA REGION 

Uo So So Re 

S K V O R T S O V . So A o 

Io Vo KURCHATOV INSTITUTE OF ATOMIC 

ENERGY 

MOSCOW D-1B2 

Uo So So Ro 

SMITH, Jo 




STEEN. Ne 

BETTIS ATOMIC POWER LABORATORY 

Po Oo BOX 79 

WEST MIFFLIN. PA 0 15122 

Uo So Ao 

STEWART, Lo 

LOS ALAMOS SCIENTIFIC LABORATORY 


LOS ALAMCS, NEW MEXICO 87544 

Uo So Ao 

STROHM. We Wo 

MOUND LABORATORY 

PoOo BOX 32 

ftlAMISBUFG. CHIO 45342 

Uo So Ao 

SYMONDS. JoLo 

AAEC RESEARCH ESTABLISHMENT 

THE DIRECTOR'S OFFICE 

PRIVATE MAIL BAG 

SUTHERLANO, Ao So Wo 

AUSTRALIA 

TELLIER. Ho 

CENTRE D'ETUDES NUCLEA IRES DE SACLAY 

BoPo NO 2 

F-91190 GIF SuR YVETTE 

FRANCE 

TILL. Co Eo 

ARGONNE NATIONAL LABORATORY 

5700 SOUTH CASS AVENUE 

ARGONNE, ILLINOIS 60439 

Uo So Ac 

TYROR, JoGe 

HEAD, GENERAL REACTOR PHYSICS 

DIVI SIGN 


WINFRITH, DORCHESTER, DORSET 

UNITED KINGDCk 

WALKER, We He 

REACTOR PHYSICS BRANCH 

CHALK RIVER NUCLEAR LABORATORIES 

ATOMIC ENERGY OF CANADA LIMITED 

CHALK RIVER, ONTARIO 

CANADA 

•ALTON. Re Be 




Uo So Ao 

WE INSTOCK, Eo Ve 

BROOKHAVEN NATIONAL LABORATORY 

UPTON, NEW YCRK 11973 

Uo So Ao 

WALLER. Fe 


UND REAKTORTECHNIK 

KERNFORSCHUNGSZENTRUM KAPLESRUHE 

POSTFACH 3640 

D— 75 KARLSRUHE 

FEDERAL REPUBLIC OF GERN^NY 

WHITTAKER. Ao 

WINDSCALE REACTOR DEVELOPMENT LABS 

WINDSCALE WORKS 

SELLA FI ELD, CALDERBRIDGE, CUMBERLAND 

UNITED KINGDCM 

WRIGHT, So Be 


HARWELL. DIDCOT 

BERKS 0X11 ORA 

UNITED KINGDCM 

YOUNG. PeGo 




Uo So Ao 

YUMOTO. Re 

PLUTONIUM FUEL DIVISION, TOKAI WORKS, 

POWER REACTOR AND NUCLEAR FUEL 

DEVELOPMENT CORPORATICN 

MURAMATSt. TOKAI-MURA. 


JAPAN 

ZETTERSTROE*. 

HoOo 

RESEARCH INSTITUTE OF NATIONAL DEFENCE 

DEPARTMENT 4 

S-104 50 STOCKHOLM 80 

SWEDEN

LIST OF ELEMENTS 

H 

1 

HYCROGEN 

KR 36 KRYPTON 

LU 71 LUTETIUM 

HE 

2 

HELIUM 

RB 37 RUBIDIUM 

HF 72 HAFNIUM 

LI 

3 

L TTHIUM 

SR 38 STRONTIUM 

TA 73 TANTALUM 

BE 

4 

BERYLLIUM 

Y 39 YTTRIUM 

W 74 TUNGSTEN 

B 

5 

BOFON 

ZR 40 ZIRCCNIUM 

RE 75 RHENIUM 

C 

6 

CARBON 

NB 41 NIOEIUM 

OS 76 OSMIUM 

N 

7 

NITROGEN 

MO 42 MOLYBDENUM 

IR 77 IRIDIUM 

0 

e 

OXYGEN 

TC 43 TECHNETIUM 

PT 78 PLATINUM 

F 

9 

FLUORINE 

RU 44 RUTHENIUM 

AU 79 GOLD 

NE 

I o 

NE CN 

RH 45 RHODIUM 

HG 80 MERCURY 

NA 

II 

SODIUM 

PD 46 PALLADIUM 

TL 81 THALLIUM 

MG 

12 

MAC-NES IUM 

AG 47 SILVER 

PB 82 LEAD 

AL 

13 

ALLMINUM 

CD 48 CADMIUM 

BI 83 BISMUTH 

SI 

14 

SILICON 

IN 49 INDIUM 

PO 84 POLONIUM 

P 

1 5 

PHOSPHCRLS 

SN 50 TIN 

AT 85 ASTATINE 

S 

16 

SULFUR 

SB 51 ANTIMONY 

RN 86 RADON 

CL 

1 7 

CHLORINE 

TE 52 TELLURIUM 

FR 87 FRANCIUM 

AR 

18 

ARGON 

I 53 IODINE 

RA 88 RADIUM 

K 

1 9 

POTASSIUM 

XE 54 XENON 

AC 89 ACTINIUM 

CA 

20 

CA LCIUM 

CS 55 CESIUM 

TH 90 THORIUM 

SC 

21 

SCAND ILM 

BA 56 BARIUM 

PA 91 PROTACTINIUM 

TI 

22 

TITANIUM 

LA 57 LANTHANUM 

U 92 URANIUM 

V 

23 

VANADILM 

CE 58 CERIUM 

NP 93 NEPTUNIUM 

CR 

24 

CHRCMIUM 

PR 59 PRASEODYMIUM 

PU 94 PLUTONIUM 

MN 

25 

MANGANESE 

ND 60 NEODYMIUM 

AM 95 AMERICIUM 

FE 

26 

I RCN 

PM 61 PROMETHIUM 

CM 9 6 CURIUM 

CO 

27 

COBALT 

SM 62 SAMARIUM 

BK 57 BERKELIUM 

N I 

28 

NICKEL 

EU 63 EUROPIUM 

CF 98 CALIFORNIUM 

CU 

29 

COPPER 

GD 64 GADOLINIUM 

ES 99 EINSTEINIUM 

ZN 

30 

ZINC 

TB 65 TERBIUM 

FM 100 FERMIUM 

GA 

31 

GALLIUM 

DY 66 DYSPROSIUM 

MO 101 MENDELE VIUM 

GE 

32 

GERMANIUM 

HO 67 HOL MIUM 

NO 102 NOBEL IUM 

A S 

33 

ARSENIC 

ER 68 ERBIUM 

LR 103 LAWRENCIUM 

SE 

34 

SELENI.LM 

TM 69 THULIUM 

KU 104 KURCHATOVIUM 

8R 

35 

BRCMINE 

YB 70 YTTERBIUM

INDC(SEC)-46/U+R+F+SIN DC INTERNATIONAL NUCLEAR DATA ...

Create successful ePaper yourself

Delete template?

Save as template?