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D. List of Withdrawn Requests Il.viii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
* Priority 2 *
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).
* Priority 3 *
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
692357 FR 92 URANIUM 234 NEUTRON CAPTURE CROSS SECTION
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
742091 FR 92 URANIUM 239 NEUTRON CAPTURE CROSS SECTION
671114 USA 93 NEPTUNIUM 237 NEUTRON CAPTURE CROSS SECTION
671116 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
671117 USA 93 NEPTUNIUM 238 NEUTRON CAPTURE 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
691345 USA 96 CURIUM 244 NEUTRON FISSION CROSS SECTION
691347 USA 96 CURIUM 245 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
691352 USA 96 CURIUM 248 NEUTRON FISSION 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
28 NICKEL 60 ooooooooooooooo IIo 26
26 NICKEL 61 ooooooooooooooo IIo 26
26 NICKEL 62 ooooooooooooooo IIo 27
26 NICKEL 64 ooooooooooooooo lie 27
25 COPPER 63 oooooooooocoooo Ilo 27
25 COPPER 65 ooooooooooooooo lie 28
3 C ZINC 64 ooooooooooco^ooo 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
40 ZIRCONIUM 55 ooooooooooooooo IIo 33
40 ZIRCONIUM 56 ooooooooooooooo IIo 34
41 NIOBIUM 53 ooooooooooooooo IIo 34
41 NIOBIUM 5= ooooooooooooooo lie 35
42 MOLYBDENUM oooo ooooooooooo IIo 35
42 MOLYBDENUM 52 ooooooooooooooo IIo 36
42 MOLYBDENUM 95 ooooooooooooooo IIo 36
42 MOLYBDENUM 56 ooooooooooooooo IIo 36
42 MOLYBDENUM 57 ooooooooooooooo IIo 37
42 MOLYBDENUM 96 ooooooooooooooo IIo 37
42 MOLYBDENUM 95 ooooooooooooooo IIo 37
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 156
GADOLINIUM 157
GADOLINIUM 156
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
PROTACTINIUM 233
PROTACTINIUM 234
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
94 PLUTONIUM 242
94 PLUTONIUM 243
94 PLUTONIUM 245
95 AMER1CIUM 241
95 AMERICIUM 242
95 AMERICIUM 243
55 AMERICIUM 244
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 250
98 CALIFORNIUM 251
98 CALIFORNIUM £52
98 CALIFORNILM 252
96 CALIFORNILM 254
95 EINSTEINIUM 252
FISSION PRODUCTS
STEEL
page
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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

3 HYDROGEN 1 NEUTHCN DIFFERENTIAL ELASTIC CROSS SECTION
.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,
M: NEW REQUEST,
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
DATAo
692016 8o 00 MEV 14o 0 MEV lOoOX 2 SWO HoOoZETTERSTROEM FOA
A: ENERGY RESOLUTION 0,2 MEVc
O: SHIELDING,
FISSION LIST PAGE IIo 4

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
DATAo
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
NEW EVALUATION TO BE DONE IF NEW EXPERIMENTAL
DATAo
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
FISSION LIST PAGE IIo 6

44 HYDROGEN 1 NEUTHCN DIFFERENTIAL ELASTIC CROSS SECTION
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
FISSION LIST PAGE IIo 1

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
M: NEW REQUEST;
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,
PRIORITY 2 ACCURACY 50 PERCENTc
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
M: NEW REQUEST;
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
M: NEW REQUEST;
11 SODIUM 22 NEUTRON
Z41020 I60O MEV PcB;HEMM I G
O: NEEDED FOR COOLANT ACTIVATIONc
M: NEW REQUEST,
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
FISSION LIST PAGE IIo 11

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
A: INCIDENT ENERGY RESOLUTION 200 KEVo
O: NEEDED FOR NEUTRON ACTIVATION ANALYSIS AND CROSS
SECTION SYSTEMATICSo
19 POTASS IUM 41
65 3S1£ 1 4o 0 MEV lOo OX N JoCSlKAI KOS
A: INCIDENT ENERGY RESOLUTION 200 KEVc
O: NEEDED FOR NEUTRON ACTIVATION ANALYSIS AND CROSS
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
M: NEW REQUESTc
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
0: FOR USE AS A FLUENCE MONITORo
FISSION LIST PAGE IIo 10

21 SCANDIUM 45 NEUTRCN CAPTURE CROSS SECTION (CONTINUED)
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
0: FOR FAST REACTOR CALCULATIONSc
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©
A: ENERGY RESOLUTION 100 KEVo
0: FOR USE AS A FLUENCE MONITORo
£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
GREATER THAN 10 PERCENT DISCREPANCY BETWEEN
INTEGRAL AND DIFFERENTIAL MEASUREMENTSo
FISSION LIST PAGE IIo 11

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),
O: ACTIVATION DETECTOR,
242127 2,10 ME V 7,00 MEV 5,OX 2 EUR NEUTRON DOSIMETRY GROUP GEL
O: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING
METHODS,
GREATER THAN 10 PERCENT DISCREPANCY BETWEEN
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
A: ENERGY RESOLUTION 100 KEVo
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
O: ACTIVATION DETECTOR,
242128 60 60 MEV 12,8 MEV 5o OX 2 EUR NEUTRON DOSIMETRY GROUP GEL
0: FOR NEUTRON COSIMETRY USING SPECTRUM UNFOLDING
METHODS,
GREATER THAN 10 PERCENT DISCREPANCY BETWEEN
INTEGRAL AND DIFFERENTIAL MEASUREMENTSo
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
M: NEW REQUEST,
23 VANADIUM_ NEUTRON__ DIFFERENTIAL ELASTIC CROSS SECTION
621305 1 o40 MEV 1 Oc 0 MEV ICoOX 3 USA CcEcTILL ANL
Po Be HEMMIG
AEC
A: ENERGY RESOLUTION 500 KEVo
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
FISSION LIST PAGE IIo 12

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 C^OSS 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
SPECTRA AT SEVERAL ANGLES IF SIGNIFICANTLY
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
0: FOR FAST REACTOR CALCULATIONSc
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
0: FOR FAST REACTOR CALCULATIONSc
Z53042 25c 3 MV 20c0 MEV 3oOX 2 INC Go 8, GAR G TRM
O: REQUIRED FOR STRUCTURAL-MATERIAL CALCULATIONSo
M: NEW REQUEST,
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
FISSION LIST PAGE IIo 13

24 SCANDIUM 45 NEUTRCN CAPTURE CROSS SECTION (CONTINUED)
241031 1o 00 KEV 20oC MEV 3cOX 2 USA B,HUTCHINS GE3
A: 5 PERCENT ACCURACY IN DFEP MINIMA,
M: NEW REQUEST,
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,
M: NEW REQUEST,
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
M: NEW REQUEST,
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,
M: NEW REQUEST,
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
SPECTRA AT SEVERAL ANGLES IF SIGNIFICANTLY
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
FISSION LIST PAGE IIo 11

£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
M: NEW REQUEST,
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
0: FOR FAST REACTOR CALCULATIONSo
UK UKNDC - AVAILABLE ESTIMATES OF FISSICN SPECTRUM AVERAGE DIFFER BY A FACTOR OF 5. MAINLY DUE TO
UNCERTAINTY IN CR-50(N,P) o
FISSION LIST PAGE IIo 15

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 ^AST 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
M: NEW REQUEST,
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
NEUTRON WIDTH, GAMMA WIDTH, SPIN AND PARITY
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
NEUTRON WIDTH, GAMMA WIDTH, SPIN AND PARITY
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
FISSION LIST PAGE IIo 16

£5 ~IANGA.NE.SC 55 TOTAL CROSS SECTION
74HSS
F;G:PEREY
0: NEED VALUES IN FE wINOOWSc
M: NEW REQUEST,
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
o: FOR FAST REACTOR CALCULATIONSc
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;
GREATER THAN 10 PERCENT DISCREPANCY BETWEEN
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
0: FOR FAST REACTOR CALCULATIONSc
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
FISSION LIST PAGE IIo 17

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
M: NEW REQUEST;
DIFFERENTIAL ELASTIC CROSS SECTION
£91564 7o 00 MEV 14o0 MEV 9oOX RcEHRLICH
ENERGY RESOLUTION ICO KEV;
ANGULAR RESOLUTION 5 DEGREESo
691.085 3oC0 MEV USA Co Ec CLIFFORD ORL
0: REQUIRED AT SEVERAL PEAKS AND VALLEYSo
A: ENERGY RESOLUTION 1 PERCENTo
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
M: NEW REQUEST;
£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
M: NEW REQUESTC
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
SPECTRA AT SEVERAL ANGLES IF SIGNIFICANTLY
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
SPECTRA AT SEVERAL ANGLES IF SIGNIFICANTLY
ANISOTROPIC©
A: RESOLUTION 20 KEV FOR INCIDENT AND SCATTERED
NEUTRONSo
M: SUBSTANTIAL MOD IFICATIONSo
FISSION LIST PAGE IIo 18

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
O: FOR FAST REACTOR CALCULATIONSo
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
0: FOR CRITICAL ASSEMBLIESc
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
o: FOR FAST REACTOR CALCULATIONSc
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
0: FOR FAST REACTORSo
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
0: FOR FAST REACTOR CALCULATIONSo
Z12024 1o 00 EV loOO MEV lOoOX D Ho HAEGGBLOM AE
0: FOR FAST REACTOR CALCULATIONSc
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,
M: NEW REQUEST,
.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,
M: NEW REQUEST,
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
0: FOR FAST REACTOR CALCULATIONS,
-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
A: ENERGY RESOLUTION 250 KEVo
0: FOR USE AS A FLUENCE MONITORo
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
NEUTRON WIDTH, GAMMA WIDTH, SPIN AND PARITY
WANTEOc
M: NEW REQUEST,
-STATUS
26 IRON 56 NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION
6S3SI4 L L B, AGH IN A IEN
0: GAMMA SPECTRA BETWEEN RESONANCES WANTED,
O: SPECIAL INTEREST ON INTERFERENCE AND DIRECT
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
FISSION LIST PAGE IIo 21

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
NEUTRON WIDTH, GAMMA WIDTH, SPIN AND PARITY
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
M: NEW REQUESTc
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) F^UENCE
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
o: FOR FAST REACTOR CALCULATIONSo
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,
0: FOR USE AS A FLUENCE MONITORo
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
0: FOR FAST REACTOR CALCULATIONSo
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
O: SPECIAL INTEREST ON INTERFERENCE AND DIRECT
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
M: NEW REQUEST,
28 NICKEL _ NEUTRON _ DIFFERENTIAL ELASTIC CROSS SECTION
591110 1o 50 MEV 14o 0 MEV 9oOX 1 USA RoEHRLlCH KAP
A: ENERGY RESOLUTION 100 KEVo
ANGULAR RESOLUTION 5 DEGREESo
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
M: SUBSTANTIAL MODIFICATIONS,
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,
M: NEW REQUESTc
FISSION LIST PAGE IIo 23

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
SPECTRA AT SEVERAL ANGLES IF SIGNIFICANTLY
AN I SO TROPI C:
ENERGY RESOLUTION - 10 PERCENT FOR INCIDENT AND
SCATTERED NEUTRON REQUIRED TO DETERMINE MAJOR
STRUCTURE:
SUBSTANTIAL MOD IFICATIONSo
.7.02.006 15o0 MEV FR JoY;BARRE CAD
o: FOR FAST REACTOR CALCULATIONSc
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
0: FOR FAST REACTOR CALCULATIONS,
28 NICKEL
£S2X32 1 5o 0 MEV 20o OX CcOEVILLERS
o: FOR FAST REACTOR CALCULATIONSc
EVALUATION MAY BE SUFFICIENTo
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
o: FOR FAST REACTOR CALCULATIONSo
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),
O: ACTIVATION DETECTOR,
EVALUATION MAY BE SUFFICIENTo
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
FISSION LIST PAGE IIo 25

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
M: NEW REQUESTc
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
A: ACCURACY REQUIRED TO BETTER THAN 20o PERCENTo
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
M: NEW REQUESTc
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
NEUTRON WIDTH, GAMMA WIDTH, SPIN AND PARITY
WANTEOo
M: NEW REQUESTo
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
0: ACTIVATION DETECTORo
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
0: ACTIVATION DETECTORo
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
M: NEW REQUESTc
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
0: FOR USE AS A FLUENCE MONITORo
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
FISSION LIST PAGE IIo 27

2 9 COPPER 62 NEUTRCN N,2N (CONTINUED)
242130 1lo9 ME V 16o 4 MEV 5 = OX 2 EUR NEUTRCN DOSIMETRY GROUP GEL
0: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING
METhODSo
GREATER THAN 10 PERCENT DISCREPANCY BETWEEN
INTEGRAL AND DIFFERENTIAL MEASUREMENTSo
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
0: FOR USE AS A FLUENCE MONITORo
242120 6o 1 0 MEV 11,3 MEV SoOX 1 EUR NEUTRON DOSIMETRY GROUP GEL
O: ROUTINE FAST NEUTRON FLUENCE MONITORo
STATUS : STATUS
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
0: FOR NEUTRON YIELD MONITORo
6£201B 1 5o 0 MEV 2 Co 0 MEV SoOX 1 JAP YoKANDA KYU
0: FOR NEUTRON YIELD MONITORo
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
A: INCIDENT ENERGY RESOLUTION 200 KEVo
O: NEEDED FOR NEUTRON ACTIVATION ANALYSIS AND CROSS
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
O: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING
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
FISSION LIST PAGE IIo 28

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
FISSICN LIST PAGE IIo 29

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;
M: SUBSTANTIAL MODIFICATIONS,
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
M: SUBSTANTIAL MODIFICATIONSo

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
M: SUBSTANTIAL MODIFICATIONSo
»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
M: NEW REQUESTo
FISSICN LIST PAGE IIo 31

40 ZIRCONIUM 91 N^UTRCN 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
ENERGY TO INCLUDE LOWEST RESOLVED RESONANCEo
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
0: TO COMPUTE DIRECT INELASTIC SCATTERING AND
INVESTIGATE ISOTOPIC SPIN-DEPENDENT COUPLING
BETWEEN GROUND AND EXCITED STATESo
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
ENERGY TO INCLUDE LOWEST RESOLVED RESONANCEo
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
M: NEW REQUESTc
FISSION LIST PAGE IIo 32

"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
0: TO COMPUTE DIRECT INELASTIC SCATTERING AND
INVESTIGATE ISOTOPIC SPIN-DEPENDENT COUPLING
BETWEEN GROUND AND EXCITED STATESo
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
40 ZIRCONIUM 94 NEUTRCN CAPTURE CROSS SECTION
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
Q: NEUTRON AND CAPTURE WIDTH NEEDEDo
O: VERIFICATION REQUIRED INCLUDES RECENT RPJ RESULTSc
40 ZIRCONIUM 95 NEUTRCN CAPTURE CROSS SECTION
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
M: SUBSTANTIAL MODIFICATIONSo
621011 1 Oo 0 KEV RcEHRLlCH KAP
a: RADIOACTIVE TARGET, 65 OAYo
THERMAL CROSS SECTION AND RI WANTEDo
A: ACCURACY 10 PERCENT IF CROSS SECTION GREATER THAN
100 BARNS AND 2C 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 1000
BARNSo
O: THE DECAY IS TO AN IMPORTANT FISSION PRODUCTo
M: NEW REQUESTc
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
M: NEW REQUESTc
FISSION LIST PAGE IIo 33

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©
M: NEW REQUEST,
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,
M: NEW REQUEST,
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
M: NEW REQUEST,
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
0: FOR FAST REACTOR CALCULATIONS,
__ _ 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
0: FOR FAST REACTOR CALCULATIONSc
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
M: NEW REQUESTc
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©
M: NEW REQUEST,
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
0: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING
METhODSc
GREATER THAN 10 PERCENT DISCREPANCY BETWEEN
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
0: FOR FAST REACTOR CALCULATIONSo
41 NIOBIUM 93 NEUTRCN N,ALPHA
Z1203S 1 So 0 MEV 30 o OX 3 FR JoYo BARRE CAD
0: FOR FAST REACTOR CALCULATIONSc
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
SPECTRA AT SEVERAL ANGLES IF SIGNIFICANTLY
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
0: FOR FAST REACTOR CALCULATIONSo
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
0: FOR FAST REACTORSc
202216 500o EV lo 00 MEV 25o OX 2 FR JoYoBARRE CAD
0: FOR FAST REACTOR CALCULATIONSo
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
0: FOR FAST REACTOR CALCULATIONS,
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
O: ACTIVATION DETECTOR,
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
M: NEW REQUEST,
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
M: NEW REQUEST,
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
FISSION LIST PAGE IIo 36

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
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
FISSION PRODUCT EFFECT IN FAST RcACTORSO
Z52006 6Co C KEV 4OOo KEV 2Co3X
ScIIJIMA
HoMATSUNOBU
NPG
SAE
0: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
o: FOR FAST REACTOR CALCULATIONSo
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
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
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
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 1000
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
0: FISSION PRODUCT EFFECT IN FAST REACTORSo
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
o: CALCULATION OF FISSION PRODUCT POISON FOR FAST
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
0: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA ABOVE 100 EVo
M: NEW REQUESTc
-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
RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
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
0: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA EXCEPT 3 DATA POINTS AT 2,
24 AND 190 KEVo
M: NEW REQUESTC
-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
IN RESONANCE INTEGRAL IF GREATER THAN 1900
BARNS AND 20 PERCENT IF BETWEEN 100 AND 1000
BARNSc
O: WANTED FOR FISSION PRODUCT POISON CALCULATIONS IN
THERMAL REACTORSo
691504 2 So 3 MV N W c He WALKER CRC
A: ACCURACY REQUIRED 35 Be
o: FISSION PRODUCT, UNKNOWN CROSS SECTIONo
241025 loCO KEV 1 Oo 0 MEV RoEcSCHENTER HED
Q: RADIOACTIVE TARGET 39o6 DAYo
o: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSc
M: NEW REQUESTc
44 RUTHENIUM 104 CAPTURE CROSS SECTION
222055 5 C Oo E V 200o JoYcBARRE CAD
RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
FISSION PRODUCT EFFECT IN FAST REACTORSo
241081
1o 00
KEV
1 Oo 0 MEV
RoEcSCHENTER
HED
Q: RADIOACTIVE TARGET 4c35 MINo
o: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSc
M: NEW REQUESTC
252010
1 OOo EV
400o
30 o OX
So 11J1MA
HoMATSUNOBU
NPG
SAE
STATUS-
a: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
0: FOR FAST REACTOR CALCULATIONSo
M: NEW REQUESTc
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
0: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSc
M: NEW REQUESTC
FISSION LIST PAGE I lo 38

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
M: NEW REQUESTc
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
O: FISSION PRODUCT EFFECT IN FAST REACTORSo
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

44 RUTHENIUM 101 NEUTRON CAPTURE CROSS SECTION (CONTINUED)
741.084 1 c 00 KE V 1 Oo 0 MEV 10,OX a Rc E,SCHENTER HED
0: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSo
M: NEW REQUESTC
Z52011
Sc 11J IMA
HoMATSUNOBU
NPG
SAE
0: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
0: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA ABOVE 100 EVo
M: NEW REQUESTc
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
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
O: FISSION PRODUCT EFFECT IN FAST REACTORSo
741004
lo OC KEV 1 CoOX
Ro EoSCHENTER
HED
0: RADIOACTIVE TARGET - 6c 5 MILLION YEARSo
o: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSc
M: NEW REQUESTc
7=2012
4 OOo KEV
So I I J IMA
HoMATSUNOBU
NPG
SAE
Q: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
0: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo
M: NEW REQUESTc
-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
M: NEW REQUESTc
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
M: NEW REQUESTc
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
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
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
FISSION LIST PAGE I lo 40

44 RUTHENIUM 101 NEUTRON CAPTURE CROSS SECTION (CONTINUED)
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
M: NEW REQUEST;
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
A: ACCURACY REQUIRED TO BETTER THAN 20o 0 PERCENTo
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
M: NEW REQUEST;
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
FISSION LIST PAGE I lo 41

51 ANTIMONY 125 CAPTURE CROSS SECTION
6S1606 2 So 3 MV CAN Wo Ho WALKER CRC
A: ACCURACY REQUIRED 300 BARNSo
O: FISSION PRODUCT, UNKNOWN CROSS SECTIONo
51 ANTIMONY 127 NEUTRON CAPTURE CROSS SECTION
651605 2 So 3 WV N WoHc WALKER CRC
A: ACCURACY REQUIRED 4000 BARNSo
O: FISSION PRODUCT, UNKNOWN CROSS SECTIONo
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
A: ACCURACY REQUIRED 900 BARNSo
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
FOR CALCULATION OF FISSION PRODUCT POISONSo
SUBSTANTIAL MODIFICATIONSo
53 IODINE 127
242134 1Oo0 MEV 14o 6 MEV SoOX 2 EUR NEUTRON DOSIMETRY GROUP GEL
0: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING
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
ENERGIES ABOVE 1 EV OF INTEREST TO GIVE 10 PERCENT
ACCURACY IN RESONANCE INTEGRALo
FISSION PROOUCTo
SUBSTANTIAL MOD IFICATIONSo
232064 lOoO MV SoOO KEV lOoOX FR Ho TELL IER SAC
0: REACTOR CALCULATIONSo
FISSION LIST PAGE IIo 42

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
0: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo
M: NEW REOUESTo
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
THERMAL CROSS SECTION AND RESONANCE INTEGRAL
WANTEDo
O: FOR FISSION PRODUCT POISON CALCULATIONSo
M: NEW REQUESTc
STATUS
STATUS
MCM KENNETT+ - ^IN 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
THERMAL CROSS SECTION AND RESONANCE INTEGRAL
WANTED TO 3 PERCENTo
0: FOR FISSION PRODUCT POISON CALCULATIONSo
M: NEW REQUESTC
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
O: FISSION PRODUCT EFFECT IN FAST REACTORSo
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
O: FOR FAST REACTOR CALCULATIONSo
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
O: FOR FISSION PRODUCT POISON CALCULATIONSo
M: SUBSTANTIAL MODIFICATIONSo
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
M: NEW REQUESTo
FISSION LIST PAGE IIo 59

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
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
0: FISSION PRODUCT EFFECT IN FAST REACTORSo
252015 100c EV 4 OOo KEV 20 o 0 X 1 JAP So I IJ IMA NPG
HoMATSUNOBU
SAE
0: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
0: FOR FAST REACTOR CALCULATIONSo
M: NEW REQUEST,
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
RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
FISSION PRODUCT EFFECT IN FAST REACTORSo
241090 1o 00 MV 1Oo 0 KEV lOoOX NcSTEEN BET
RADIOACTIVE TARGET - 3o 3 MILLION YEARSo
THERMAL CROSS SECTION AND RESONANCE INTEGRAL
WANTED,
FOR FISSION PRODUCT POISON CALCULATIONSo
NEW REQUEST,
241391 1o 00 KEV
10o0 MEV lOoOX RoEoSCHENTER HED
0: RADIOACTIVE TARGET - 3c 3 MILLION YEARSo
O: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSc
M: NEW REQUEST,
252016 1 OOo EV
So 11J IMA
HoMATSUNOBU
NPG
SAE
O: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
0: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo
M: NEW REQUESTc
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
O: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSo
M: NEW REQUESTC
59 PRASEODYMIUM 141 CAPTURE CROSS SECTION
241092 1o 00 MV
1Oo 0 KEV lOoOX NoSTEEN BET
0: THERMAL CROSS SECTION AND RESONANCE INTEC
WANTEDo
0: FOR FISSION PRODUCT POISON CALCULATIONSo
RESOLVE UNCERTAINTIES IN AVAILABLE DATA,
M: NEW REQUESTc
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
FISSION LIST PAGE IIo 44

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:
THERMAL CROSS SECTION AND RESONANCE INTEGRAL
WANTED:
ENERGIES ABOVE lot EV OF INTEREST TO GIVE 10
PERCENT IN RESONANCE INTEGRALo
FOR CALCULATION OF FISSION PRODUCT POISONSo
SUBSTANTIAL MODIFICATIONSo
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
Q: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
o: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo
M: NEW REQUESTo
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
M: SUBSTANTIAL MODIFICATIONSo
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
o: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSc
M: NEW REQUESTc
252016 1 COo EV 400o KEV 20o OX 1 JAP So I IJ IMA NPG
HoMATSUNOBU
SAE
0: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
o: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo
M: NEW REQUESTc
STATUS
STATUS
SAC RIBONo - 72B0LCGNA 1 235. EVALUATION FROM 0oC2S EV TO 30 KEVc ALSO FISSION NEUTRON SPECTRUM AVERAGE
HAR CABELL+ - ^IN 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
FISSION LIST PAGE I lo 45

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
THERMAL CROSS SECTION AND RESONANCE INTEGRAL
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
M: SUBSTANTIAL MODIFICATIONSo
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
THERMAL CROSS SECTION AND RESONANCE INTEGRAL
WANTEOo
ENERGIES ABOVE IcO EV OF INTEREST TO GIVE 10
PERCENT IN RESONANCE INTEGRALo
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
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
0: FISSION PRODUCT EFFECT IN FAST REACTORSo
252015 1OOo EV 400o KEV 20o0X 1 JAP So I IJ IMA NPG
HoMATSUNOBU
SAE
0: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
o: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA FROM 100 EV TO 400 KEVo
M: NEW REQUESTo
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
THERMAL CROSS SECTION AND RI WANTEDo
ENERGIES ABOVE loC EV OF INTEREST TO GIVE 10
PERCENT IN RESONANCE INTEGRALo
FOR CALCULATION OF FISSION PRODUCT POISONSo
SUBSTANTIAL MODIFICATIONSo
621046 1 o 00 MV lo 00 KEV lOoOX USA NoSTEEN
BoHUTCHINS
RoEHRLICH
BET
GEB
KAP
RADIOACTIVE TARGET - 5o 3 7 DA Yc
THERMAL CROSS SECTION AND RI WANTEDo
LOOK FOR 1/V ABOVE 1 EVc
FOR FISSION PRODUCT POISON CALCULATIONSo
SUBSTANTIAL MODIFICATIONSo
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
THERMAL CROSS SECTION AND RI WANTEDo
ACCURACY 10 PERCENT WANTED IF CROSS SECTION
GREATER THAN 10CC BARNS. 20 PERCENT IF BETWEEN
15 AND 1000 BARNSo
ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO 10 PERCENT IF GREATER THAN 10000
BARNS OR 20 PERCENT IF BETWEEN 1000 AND 10000
BARNSo
SUBSTANTIAL MODIFICATIONSo
61 PROMETHIUM 151 NEUTRCN CAPTURE CROSS SECTION
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
M: SUBSTANTIAL MODIFICATIONSo
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
A: INCIDENT ENERGY RESOLUTION 200 KEVo
0: NEEDED FOR NEUTRON ACTIVATION ANALYSIS AND CROSS
SECTION SYSTEMATICSo
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
0: RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
0: FISSION PRODUCT EFFECT IN FAST REACTORSo
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
0: RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
O: FISSION PRODUCT EFFECT IN FAST REACTORSo
241595 loOO KEV 1Oo 0 MEV lOoOX 1 USA RoEoSCHENTER HED
0: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSc
M: NEW REQUESTo
252525 1 00© EV 400o KEV 20o0X 1 JAP SoIIJIMA NPG
HoMATSUNOBU
SAE
0: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
0: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA EXCEPT A MEASUREMENT AT
30 KEVo
M: NEW REOUESTo
STATUS
STATUS
SAC RIBONo - 72B0LCGNA 1 235. REVIEWo
62 SAMARIUM 150 NEUTRCN CAPTURE CROSS SECTION
621552 1o00 MV lo 00 KEV 1 USA NoSTEEN BET
BoHUTCHINS
GEB
0: THERMAL CROSS SECTION AND RI WANTEDo
A: ACCURACY REQUIRED - 2 TO 5 PERCENTo
ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO BETWEEN 2 AND 3 PERCENTo
0: FOR CALCULATION OF FISSION PRODUCT POISONSo
M: SUBSTANTIAL MODIFICATIONSo
FISSION LIST PAGE I lo 51

62 SAMARIUM 151 CAPTURE CROSS SECTION
621354 lo 00 KEV NcSTEEN
So HUTCH IN S
BET
GEB
RADIOACTIVE TARGET - 93 YEARSo
THERMAL CROSS SECTION AND RI WANTEDo
DESIRED ENERGY RESOLUTION 5 PERCENTo
ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO 10 PERCENTo
WANTED FOR CALCULATION OF FISSION PRODUCT POISONSo
SUBSTANTIAL MODIFICATIONSo
232082 lOoO MV 5o 00 KEV FR Ho T ELL IER SAC
O: REACTOR CALCULATIONS,
252063 SCOo EV J o Yc BARRE CAD
RELATIVE VALUE VERSUS ENERGY OR VALUE RELATIVE
TO CAPTURE IN ANOTHER NUCLEUS SUCH AS U-238o
FISSION PRODUCT EFFECT IN FAST REACTORSo
241356
1o 00
KEV
10c 0
MEV
Ro Ec SCHENTER
HED
0: RADIOACTIVE TARGET - 93 YEARSo
0: CALCULATION OF FISSION PRODUCT POISON FOR FAST
REACTORSo
M: NEW REQUESTC
2S2S21
100c
EV
30 o 0 X
So I I J IMA
HoMATSUNOBU
NPG
SAE
O: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
0: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA FROM ICO EV TO 400 KEVo
M: NEW REQUESTc
-STATUS
SAC RIBONo - 73B0LCGNA 1 235. REVIEWo
NPG IIJ1MA+ (1575) , NO EXPERIMENTAL DATA FRCM 100 EV TO 400 KEVo
62 SAMARIUM 152 CAPTURE CROSS SECTION
£71055 lo 00 KEV NoSTEEN
BoHUTCHINS
BET
GEB
THERMAL CROSS SECTION AND RI WANTEDo
ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO 10 PERCENTo
FISSION PRODUCT POISONo
SUBSTANTIAL MODIFICATIONSo
-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
62 SAMARIUM 153 NEUTRCN CAPTURE CROSS SECTION
£21061 1c 00 MV lo 00 KEV NoSTEEN BET
RADIOACTIVE TARGET - 47 HOURSo
THERMAL CROSS SECTION AND RI WANTEDo
ACCURACY OF 10 PERCENT REQUIRED IF CROSS SECTION
GREATER THAN 30000 BARNS. 20 PERCENT IF LOWERo
ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO 20 PERCENT IF BETWEEN 30 AND 300
BARNS OR 10 PERCENT IF LARGERo
FOR CALCULATION OF FISSION PRODUCT POISONSo
SUBSTANTIAL MODIFICATIONSo
£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
ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO 20 PERCENT IF BETWEEN 30 AND 300
BARNS OR 10 PERCENT IF LARGERo
FOR CALCULATION OF FISSION PRODUCT POISONSo
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
M: NEW REQUEST,
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
MEASURED ACTIVATION RATES BY MEANS OF FOILS
(ESPECIALLY SPECTRAL INDICES) FOR THERMAL
NEUTRON FLUXESo
FISSION LIST PAGE IIo 49

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
0: REACTOR CALCULATIONSo
Z.411Q3 5o 00 KEV 1 0,0* A NoSTEEN BET
0: THERMAL CROSS SECTION AND RI WANTEDo
0: FOR FISSION PRODUCT POISON CALCULATIONSo
M: NEW REQUEST;
7311OS 1 o 00 KEV 1o 00 MEV 1 USA Po Be HEMMIG
M: NEW REQUESTc
Z52022 4Oo 0 KEV 400o 30,0* So I IJ IMA
HoMATSUNOBU
NPG
SAE
Q: DESIRED WITH LOWER PRIORITY FOR WIDER ENERGY RANGE
O: FOR FAST REACTOR CALCULATIONSo
NO EXPERIMENTAL DATA FROM 40 KEV TO 400 KEVo
M: NEW REQUESTo
-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
M: NEW REQUESTC
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
THERMAL CROSS SECTION AND RI WANTEDo
RESONANCE PARAMETERS WANTED,
A: ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO 10 PERCENTo
O: FOR CALCULATION OF FISSION PRODUCT POISONS,
M: SUBSTANTIAL MODIFICATIONS,
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,
ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO 10 PERCENTo
FOR CALCULATION OF FISSION PRODUCT POISONSo
SUBSTANTIAL MODIFICATIONSo
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,
M: NEW REQUESTc
FISSION LIST PAGE 11, 50

61 PROMETHIUM 145 NEUTRCN CAPTURE CROSS SECTION
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
A: ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO 5 PERCENTo
0: NEEDED TO DEFINE NEGATIVE ENERGY RESONANCE IN
EITHER GD-155 OR GD-157o
M: SUBSTANTIAL MODIFICATIONSo
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
M: SUBSTANTIAL MODIFICATIONSo
64 GADOLINIUM 156 NEUTRON CAPTURE CROSS SECTION
621523 1O 00 MV loOO KEV A BoHUTCHINS GEB
A: ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
INTEGRAL TO 5 PERCENTo
0: FOR CALCULATING OF BURN UP IN THERMAL REACTORSo
64 GADOLINIUM I 56 NEUTRCN RESONANCE PARAMETERS
651162 2o 00 KEV BoHUTCHINS GEB
Q: NEUTRON AND CAPTURE WIDTH NEEDEDo
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
FISSION LIST PAGE I lo 51

61 PROMETHIUM 145 NEUTRCN CAPTURE CROSS SECTION
6 7-1074 CO 50 EV 1o 00 KEV 5oOX A Eo HUTCHINS GEB
A: ENERGIES ABOVE 1 EV OF INTEREST TO GIVE RESONANCE
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
ENERGY TO INCLUDE LOWEST RESOLVED RESONANCEo
0: TO VERIFY'-EXISTING MEASUREMENTSo
M: NEW REQUESTO
64 GADOLINIUM 160 RESONANCE PARAMETERS
241110 2o00 KEV BOHUTCHINS GEB
O: ELASTIC AND GAMMA WIDTH WANTEDo
ENERGY TO INCLUDE LOWEST RESOLVED RESONANCEo
0: TO VERIFY EXISTING MEASUREMENTSo
M: NEW REQUEST,
66 DYSPROSIUM 161 NEUTRON RESONANCE PARAMETERS
652283 200c EV 3 ITY Vc BENZI BOL
0: PARTIAL RADIATION WIDTHS NEEOEOo
A: ACCURACY REQUIRED TO BETTER THAN 15o PERCENTo
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
MEASURED ACTIVATION RATES BY MEANS OF FOILS
(ESPECIALLY SPECTRAL INDICES) FOR THERMAL
NEUTRON FLUXESo
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
A: ACCURACY REQUIRED TO BETTER THAN 15o PERCENTo
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
M: NEW REQUESTO
FISSION LIST PAGE I lo 51

68 ERBIUM 168 NEUTRCN N«ALPHA
£55030 2 So 3 MV lOoOX 3 HUN JoCSIKAI KOS
0: FOR NEUTRON ACTIVATION ANALYSIS AND CROSS SECTION
SYSTEMATICS WANTEDo
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
O: ACTIVATION DETECTORo
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
0: ACTIVATION DETECTORo
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
0: ACTIVATION DETECTORo
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
FISSION LIST PAGE IIo 53

71 LUTETIUM 176 NEUTPCN CAPTURE CROSS SECTION (CONTINUED)
fiaaaat 10o0 EV CoALBERT ROS
STATUS
CROSS SECTION DATA NEEDED FOR EVALUATION OF
MEASURED ACTIVATION RATES BY MEANS OF FOILS
(ESPECIALLY SPECTRAL INDICES) FOR THERMAL
NEUTRON FLUXESo
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
MEASURED ACTIVATION RATES BY MEANS OF FOILS
(ESPECIALLY SPECTRAL INDICES) FOR THERMAL
NEUTRON FLUXESo
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
SUBSTANTIAL MODIFICATIONSo
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
M: SUBSTANTIAL MODIFICATIONSO
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
ABOVE 100 EV. 20 PERCENT ACCURACY REQUIREDo
AVERAGE P-WAVE CAPTURE WIDTH TO 20 PERCENTo
S-WAVE STRENGTH FUNCTION TO 40 PERCENTo
TO RESOLVE DISCREPANCIES IN RESONANCE INTEGRALo
NEEDED FOR MONTE CARLO BURN UP CALCULATIONSo
SUBSTANTIAL MODIFICATIONSo
232056 1Oo 0 MV So 00 KEV lOoOX
FR HoTELLIER SAC
O: REACTOR CALCULATIONSo
STATUS
SAC RIBONo - 72B0LCGNA 1 235. PEVIEWo
FISSION LIST PAGE IIo 54

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
BETWEEN 10 AND 100 EV, TOTAL. NEUTRON AND CAPTURE
WIDTHS NEEDED WITH 10 PERCENT ACCURACYo
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
NEEDED FOR MONTE CARLO BURN UP CALCULATIONSo
M: SUBSTANTIAL MODIFICATIONSo
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
WIDTHS NEEDED WITH 10 PERCENT ACCURACYo
ABOVE 100 EV, 20 PERCENT ACCURACY REOUIREDo
7o78-EV RESONANCE WIDTH TO 3 PERCENTo
S-WAVE STRENGTH FUNCTION TO 20 PERCENTo
P-WAVE AVERAGE CAPTURE WIDTH TO 20 PERCENTo
TO RESOLVE DISCREPANCIES IN RESONANCE INTEGRALo
NEEDED FOR MONTE CARLO BURN UP CALCULATIONSo
SUBSTANTIAL MODIFICATIONSo
£92304 1 Oo 0 MV
STATUS-
5o CO KEV SoOX HoT ELL I ER SAC
Q: RESONANCE INTEGRAL ALSO WANTEDo
A: ACCURACY 1 PERCENT AT THERMAL AND 5 PERCENT FOR
RESONANCE INTEGRALO
O: EVALUATION MAY SUFFICE IF IT EXPLAINS
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
BETWEEN 10 AND 100 EV, TOTAL. NEUTRON AND CAPTURE
WIDTHS NEEDED WITH 10 PERCENT ACCURACYo
ABOVE 100 EV, 20 PERCENT ACCURACY REQUIRED©
5o 68-EV RESONANCE WIDTHS TO 5 PERCENT©
S-WAVE STRENGTH FUNCTION TO 20 PERCENTo
AVERAGE P-WAVE CAPTURE WIDTH TO 20 PERCENTo
0: TO RESOLVE DISCREPANCIES IN RESONANCE INTEGRALo
NEEDED FOR MONTE CARLO BURN UP CALCULATIONSo
M: SUBSTANTIAL MODIFICATIONS©
6S2.3Q5 1 Oo 0 MV 5© 00 KEV SoOX 1 FR Ho TELL I ER SAC
Q: RESONANCE INTEGRAL ALSO WANTEDo
A: ACCURACY 1 PERCENT AT THERMAL AND 5 PERCENT FOR
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
WIDTHS NEEDED WITH 10 PERCENT ACCURACYo
ABOVE 100 EV. 20 PERCENT ACCURACY REQUIREDo
S-WAVE STRENGTH FUNCTION TO 20 PERCENTo
AVERAGE P-WAVE CAPTURE WIDTH TO 20 PERCENTo
TO RESOLVE DISCREPANCIES IN RESONANCE INTEGRALo
NEEDED FOR MONTE CARLO BURN UP CALCULATIONSo
SUBSTANTIAL MOO IFICATIONSo
752069 lOoO
5o 00 KEV SoOX FR Ho TELL IER SAC
0: REACTOR CALCULATIONSo
STATUS —
SAC RIBONo - 72B0LCGNA 1 235, REVIEWo PROBABLY COES NOT MEET ACCURACY REQUIREMENTS©
-STATUS
FISSION LIST PAGE IIo 55

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
M: NEW REQUESTo
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
M: NEW REQUESTo
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
M: SUBSTANTIAL MODIFICATIONSo
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
0: ACTIVATION DETECTORo
STATUS • STATUS
JUL QAIMo - NP/A 242 317(1575). DATA AT 14o7 MEV FOR ENRICHED ISOTOPESo
FISSION LIST PAGE II, 56

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
SYSTEMATICS WANTEDo
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
0: ACTIVATION DETECTORo
FISSION LIST PAGE IIo 95

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
O: SPECIAL INTEREST ON INTERFERENCE AND DIRECT
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
O: SPECIAL INTEREST ON INTERFERENCE AND DIRECT
CAPTUREo
80_MERCURY 200 NEUTRON _ TOTAL PHOTON PRODUCT ION_CROSS SECTION
£52044 3 BZL L0O0 Bo AGHINA IEN
O: GAMMA SPECTRA BETWEEN RESONANCES WANTEDo
O: SPECIAL INTEREST ON INTERFERENCE AND DIRECT
CAPTUREo
80MERCURY 201 NEUTRON _ TOTAL f^OTON PRODUCTION_CROSS SECTION
£52045 3 BZL L 0O0 Bo AGHINA IEN
O: GAMMA SPECTRA BETWEEN RESONANCES WANTEDo
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
O: ACTIVATION DETECTORo
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
O: ACTIVATION DETECTORo
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
0: ACTIVATION DETECTORo
STA TUS
STATUS
ORL EARLS* - USNOC-11 197(1974). RESONANCE PARAMETERSo
FISSION LIST PAGE IIo 59

81 THALLIUM 20 5 NEUTRGN
1 5o C MEV Ao MICHAUDON
0: PRODUCTION OF TL-204 ( 3 YEAR )o
0: ACTIVATION DETECTORo
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
NEW EVALUATION TO BE DONE IF NEW EXPERIMENTAL
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
NEW EVALUATION TO BE DONE IF NEW EXPERIMENTAL
DATAo
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
SUBSTANTIAL MODIFICATIONSo
652 32.S lo 00 KEV lo 00 MEV UK Co Go CAMPBELL WIN
0: FOR FAST REACTORSc
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
M: NEW REQUESTc
253004 25o 3 MV 20o 0 MEV SoOX
C Go Be GAR G TRM
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTo
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,
M: NEW REQUESTo
242135 lo 50 MEV 7o 20 MEV EUR NEUTRON DOSIMETRY GROUP
o: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING
METHOOSo
GREATER THAN 10 PERCENT DISCREPANCY BETWEEN
INTEGRAL AND DIFFERENTIAL MEASUREMENTSo
253305
2 So 3 MV 20o 0 MEV SoOX D Go Bo GARG TRM
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTc
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
FISSION LIST PAGE IIo 61

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
0: FOR FAST REACTOR CALCULATIONSo
-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
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTc
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
M: NEW REQUESTc
90 THORIUM 233 NEUTRON INELASTIC CROSS SECTION
255005 20o 0 MEV SoOX INC Go Bo GARG TRM
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESc
M: NEW REQUESTc
90 THORIUM 233 NEUTRON CAPTURE CROSS SECTION
25500.9 2 So 3 MV 20o 0 MEV IND Gc Bo GARG TRM
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESc
M: NEW REOUESTc
90 THORIUM 233 FISSION CROSS SECTION
255010 2 So 3 MV 20o 0 MEV INC Gc Be GARG TRM
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESc
M: NEW REQUESTc
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
M: NEW REQUESTo
91 PROTACTINIUM 233 ELASTIC CROSS SECTION
255012 2 Eo 3 MV 20o 0 MEV INC Gc Be GARG TRM
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESc
M: NEW REQUESTc
91 PROTACTINIUM 233 NEUTRCN INELASTIC CROSS SECTION
255012 20o 0 MEV INC Gc Be GARG TRM
O: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REOUESTc
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
CAPTURE CROSS SECTION
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
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTC
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
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUEST,
91 PROTACTINIUM 233 NEUTRON RESONANCE PARAMETERS
652232 1OOo EV lOoOX 3 NEC MiEc Ao HERMANS VON
Q: NEUTRON AND CAPTURE WIDTH NEEDEDo
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
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUEST,
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,
M: NEW REQUEST,
91 PR0TACTINIUM_234 NEUTRON _ INELASTIC CROSS SECTION
252015 20o 0 MEV SoOX 2 INO Go Bo GARG TRM
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTo
91 PROTACTINIUM 234 NEUTRON CAPTURE CROSS SECTION
253015 2 Eo 3 MV 2 Oo 0 MEV SoOX 2 INC Go Bo GARG TRM
O: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTc
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,
M: NEW REQUEST,
92 URANIUM 232 NEUTRON CAPTURE CROSS SECTION
231133 500o EV 10,0 MEV 2 USA Ro He CAHLBERG GA
A: ACCURACY REQUIRED - 2 TO 10 PERCENTo
O: FOR FAST REACTOR BLANKETSo
M: NEW REQUESTo
92_URANIUM 233 _ HALF LIFE
231115 OoSX 1 USA NcSTEEN BET
0: TO RESOLVE DISCREPANCIES,
M: NEW REQUEST,
92URANIUM 233 _ NEUTRON TOTAL CROSS SECTION
252021 2 So 3 MV 20o 0 MEV SoOX 2 INC Go Bo GARG TRM
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTo
FISSION LIST PAGE IIo 63

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
M: NEW REQUESTO
92 URANIUM 233 NEUTRON INELASTIC CROSS SECTION
253022 20o 0 MEV 5c 0 X IND Gc Be GARG TRM
O: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESc
M: NEW REQUESTo
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
0: FOR FAST REACTORSo
M: SUBSTANTIAL MODIFICATIONSo
92 URANIUM 233
CAPTURE CROSS SECTION
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,
M: NEW REQUESTC
U—2 33/THORIUM REACTOR
253324 2=0 3 MV 20o0 MEV D Go Bo GARG TRM
O: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUEST,
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
SUBSTANTIAL MODIFICATIONSo
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
SUBSTANTIAL MODIFICATIONSo
£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
O: FOR FAST REACTORSo
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,
M: NEW REQUEST,
Z41114
A NoSTEEN BET
Q: U-233 FISSION SPECTRUM AVERAGE VALUE NEEDEDo
0: FOR ANALYSIS OF TARGET FAST MULTIPLICATION,
M: NEW REQUEST,
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
A: ACCURACY REQUIRED - 1 TO 3 PERCENTo
0: TO LOOK FOR STRUCTURE BELOW 1 MEVo
M: SUBSTANTIAL MODIFICATIONSo
651230
30o0
KEV
3o 00
MEV
Ro H, DAHLBERG
AoMoPERRY
GA
ORL
A: ACCURACY REQUIRED - 1 TO 3 PERCENTo
0: TO LOOK FOR STRUCTURE BELOW 1 MEVo
M: NEW REQUEST,
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
SUBSTANTIAL MODIFICATIONSo
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,
M: NEW REQUESTO
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
M: NEW REQUEST,
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
0: FOR CALCULATION OF FISSION PRODUCT POISONSo
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
o: FOR FAST REACTOR CALCULATIONSc
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
0: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTo
92URANIUM 234 NEUTRCN _ ELASTJCCROSS SECTION
255522 2 So 3 MV 2 Oo 0 MEV SoOX 2 INC Go Be GARG TRM
O: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESc
M: NEW REQUESTc
92 URANIUM 234 NEUTRON INELASTIC CROSS SECTION
255525 20o 0 MEV SoOX 2 INC Go Bo GARG TRM
O: REQUIRED FOR THORIUM FUEL-CYCLE STUD IE So
M: NEW REQUESTc
92 URANIUM 234 NEUTRON CAPTURE CROSS SECTION
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
O: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTo
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
FISSION LIST PAGE 1 lo 83

92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION (CONTINUED)
223030 2Eo 3 MV 20o0 MEV SoOX 2 INO Go Ec GARG TRM
O: REQUIRED FOR THORIUM FUEL-CYCLE STUDIESo
M: NEW REQUESTo
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
0: FOR CRITICAL ASSEMBLIESc
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
0: FOR CRITICAL ASSEMBLIESo
253023 800o KEV So 00 MEV L oN,USACHEV FEI
A: FROM 0 c 8 - lc 4 MEV ACCURACY 15 PERCENT,
PRIORITY 2 ACCURACY 15 PERCENTo
FROM lo 4 - 2o 5 MEV ACCURACY 17 PERCENT,
PRIORITY 2 ACCURACY 17 PERCENTo
FROM 2o 5 - 5,0 MEV ACCURACY 30 PERCENT.
PRIORITY 2 ACCURACY 30 PERCENTo
O: NEED FOR FAST REACTOR CALCULATION
FOR MORE DETAIL SEE INTRODUCTIONc
M: NEW REQUESTo
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
FISSION LIST PAGE 1 lo 83

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
O: FOR FAST REACTORSo
FOR EVALUATION OF NUCLEAR DATAo
NO EXPERIMENTAL DATA ABOVE 7o5 MEVc
M: SUBSTANTIAL MODIFICATIONSo
653052 3 OOo KEV 1 Oo 0 MEV lOoOX 1 BAN MoMc ISLAM RAM
O: FOR FAST REACTORSc
.742071 1 5o 0 MEV 20 o 0 X 2 FR AoMICHAUDON BRC
0: FOR CRITICAL ASSEMBLIESc
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
M: NEW REOUESTc
92 URANIUM 235 NEUTRCN DIFFERENTIAL TOTAL SCATTERING CROSS SECTION
252027 1o 00 KEV 1Oo 0 MEV 1 JAP He MATSUNOBU SAE
A: ACCURACY REQUIRED - 2 TO 5 PERCENTo
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 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
O: FOR FAST REACTORSc
92 URANIUM 235 NEUTRON CAPTURE CROSS SECTION
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
O: FOR FAST REACTORSc
NUCLEAR DATA EVALUATIONc
5 TO 10 PEPCENTo
PERCENTo
NO EXPERIMENTAL DATA ABOVE 2
M: SUBSTANTIAL MODIFICATIONSo
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
0: FOR FAST REACTORSc
241112 1o 00 MV lo 00 EV A NoSTEEN BET
Q: SHAPE ESPECIALLY IMPORTANT AT LOW ENERGYo
M: NEW REQUESTO
242005 200o EV SOOo KEV SWD HoHAEGGBLOM AE
O: FAST REACTOR CALCULATIONSo
242028 3o 00 MEV FR AoMICHAUDON BRC
0: FOR CRITICAL ASSEMBLIESc
FISSION LIST PAGE IIo 69

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,
PRIORITY 2 ACCURACY 10 PERCENTo
FROM OoS - Ao 5 MEV ACCURACY 50 PERCENT,
PRIORITY 2 ACCURACY 50 PERCENTo
ABOVE 4o 5 MEV REQUIREMENTS 2 TIMES WEAKER,
0: NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTIONo
M: NEW REQUESTc
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
O: FOR FAST REACTORSo
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
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
M: NEW REQUEST.
92 URANILM 235 NEUTRCN
232022 15o 0 MEV FR Ao MICHAUDON 6RC
0: FOR CRITICAL ASSEMBLIESc
92 URANIUM 235 NEUTRON FISSION CROSS SECTION
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
A: ENERGY RESOLUTION 3 PERCENTo
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,
FISSION LIST PAGE IIo 70

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
FOR FAST REACTORSc
692496 2 00c EV SOOo KEV 2oOX Ho HAEGGBLOM AE
FAST REACTOR CALCULATIONSo
693054 2 5c 3 MV 1 So 0 MEV MoMoISLAM RAM
FOR FAST REACTORSc
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
SEE GENERAL COMMENTS IN THE INTRODUCTION
REQUEST CONSIDERED FULFILLED, WHEN AT LEAST THREE
MEASUREMENTS WITH DIFFERENT METHODS AGREE WITHIN
REQUESTED ACCURACYo
SUBSTANTIAL MODIFICATIONSo
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
M: NEW REQUESTc
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
A: ENERGY RESOLUTION - 1 TO 2 PERCENTo
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
M: NEW REOUESTc
252024 1 COo KEV
loOO
MEV
JAP
HoMATSUNOBU
SAE
Q: ABSOLUTE MEASUREMENT WANTEDO
A: ENERGY RESOLUTION - 1 TO 2 PERCENTo
o: EVALUATION OF u-235 NUCLEAR DATA AND FOR REACTOR
DESIGN CALCULATIONSo
M: NEW REQUESTc
252025 loOO MEV
20o 0
MEV
HoMATSUNOBU
SAE
O: ABSOLUTE MEASUREMENT WANTEOo
A: ACCURACY REQUIRED - 1 TO 2 PERCENTo
ENERGY RESOLUTION - 1 TO 2 PERCENTo
O: EVALUATION OF U-235 NUCLEAR DATA AND FOR REACTOR
DESIGN CALCULATIONSo
THE EXPERIMENTAL DATA ARE COMPARATIVELY POOR IN
THE ENERGY RANGE ABOVE 6 MEV EXCEPT 14 MEV DATAo
M: NEW REQUEST,
FISSION LIST PAGE 1 lo 83

92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION (CONTINUED)
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
FAST REACTOR CALCULATIONSo
CS ABOVE 100 KEVo
FOR MORE DETAIL SEE INTRODUCTIONo
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
M: NEW REQUESTc
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
92 URANIUM 235 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR)
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
SUBSTANTIAL MODIFICATIONSo
742025 1 5o 0 MEV AoMICHAUDON
A: ACCURACY 2 PERCENT TO 1 KEV.
O: FOR CRITICAL ASSEMBLIES:
1 PERCENT ABOVEo
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,
PRIORITY 2 ACCURACY 1o 2 PERCENTo
ABOVE A o 5 MEV REQUIREMENTS 2 TIMES WEAKERo
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTIONo
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
FISSION LIST PAGE IIo 110

92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION (CONTINUED)
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
M: SUBSTANTIAL MODIFICATIONSo
£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 FAST REACTORSc
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
0: FOR CRITICAL ASSEMBLIESc
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
92 URANIUM 235 NEUTRON FISSION PRODUCT MASS YIELD SPECTRUM
£21105 2oOX A NoSTEEN BET
O: CUMULATIVE AND DIRECT YIELDS OF XE-135o
O: CALCULATION OF FISSION PRODUCT POISONSo
M: SUBSTANTIAL MODIFICATIONSo
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
FISSION LIST PAGE 1 lo 83

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
92 URANIUM 236 NEUTRON FISSION CROSS SECTION
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
0: FOR FAST REACTOR CALCULATIONSc
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
SUBSTANTIAL MODIFICATIONSo
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
92 URANIUM 236 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR)
212C62 5C0o 1 5O 0 MEV JoYcEARRE
A: ACCURACY RELATIVE TO NU CF-252o
o: FOR FAST REACTOR CALCULATIONSo
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,
M: SUBSTANTIAL MODIFICATIONSo
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
92 URANIUM 237 NEUTRON FISSION CROSS SECTION
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
0: FOR FAST REACTOR CALCULATIONSo
FISSION LIST PAGE 1 lo 83

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
92 URANIUM 238 NEUTRON INELASTIC CROSS SECTION
652262 15o 0 MEV JoYcEARRE CAD
0: ALTERNATE QUANTITY - NONELASTIC CROSS SECTIONo
0: FOR FAST REACTOR CALCULATIONSc
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.
PRIORITY 2 ACCURACY 10 PERCENTc
FROM 5O0-6O5 MEV ACCURACY 7o 8 PERCENT,
PRIORITY 2 ACCURACY 7c 0 PERCENTo
FROM 6o 5-1C MEV ACCURACY 10 PERCENT,
PRIORITY 2 ACCURACY 10 PERCENTc
NEED FOR FAST REACTOR CALCULATIONo
FOR MORE DETAIL SEE INTRODUCTIONo
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
M: SUBSTANTIAL MODIFICATIONSo
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
o: FOR FAST REACTOR CALCULATIONSo
632,334 7o 00 MEV 14o 0 MEV SoOX
FISSION LIST PAGE IIo 77

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
CROSS SECTION FOR INELASTIC REMOVAL BELOW FISSION
THRESHOLD OF U-238 WANTED TO lo5 - 2o 0 PERCENTo
CROSS SECTION FOR INELASTIC REMOVAL BELOW FISSION
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
0: FOR FAST REACTORSc
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
O: FOR FAST REACTORSo
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
0: FOR THERMAL REACTORSo
£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,
FISSION LIST PAGE 1 lo 83

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
O: FAST REACTOR CALCULATIONSo
£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 *
A: ACCURACY FOR AVERAGE VALUE OF THE ERROR BETWEEN
E AND 2E=
O: FOR FAST REACTORSc
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
FOR FAST REACTORSc
232032
1o 00
KEV
loOO
MEV
So I IJ IMA
NPG
A: ACCURACY REQUIRED TO BETTER THAN 5o 0 PERCENTo
o: FOR FAST REACTOR CALCULATIONSo
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
SUBSTANTIAL MODIFICATIONSo
241123 loOO EV 2 0o 0 KEV SoOX USA NoSTEEN BET
0: TO RESOLVE DISCREPANCIES AMONG INTEGRAL AND
DIFFERENTIAL EXPERIMENTSo
M: NEW REQUESTO
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
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUC TIONo
NEW REQUESTc
FISSION LIST PAGE 1 lo 83

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,
0: FOR FAST REACTORSc
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
A: LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGY AND
PHOTON SPECTRUMc
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
M: SUBSTANTIAL MODIFICATIONSo
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
M: SUBSTANTIAL MODIFICATIONSo
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
FISSION LIST PAGE 1 lo 83

92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION (CONTINUED)
653065 15o C MEV 5o 0X 1 BAN MoMc ISLAM RAM
0: FOR FAST REACTORSc
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
M: SUBSTANTIAL MODIFICATIONSo
222112 5o 00 MEV 3c 0 X 1 UK Co Gc CAMPBELL WIN
0: FOR FAST REACTORSc
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
O: FOR NEUTRON DOSIMETRY USING SPECTRUM UNFOLDING
METHODSo
GREATER THAN 10 PERCENT DISCREPANCY BETWEEN
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
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTIONo
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
M: SUBSTANTIAL MODIFICATIONSo
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
O: SEE GENERAL COMMENTS IN THE INTRODUCTION
242556 15o 0 MEV loOX 1 FR AoMICHAUDON BRC
0: FOR CRITICAL ASSEMBLIESO
FISSION LIST PAGE 1 lo 83

92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION (CONTINUED)
Z54 020 800c KEV 1 Oc 0 MEV LoNoUSACHEV FEI
FROM Oo B - lOoO MEV ACCURACY 2o1 PERCENT,
PRIORITY 2 ACCURACY loO PERCENTo
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTION
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
M: NEW REQUESTo
-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
FOR FAST REACTORSc
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,
0: NEEDED FOR FAST REACTOR CALCULATIONSo
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
SUBSTANTIAL MODIFICATIONSo
FISSION LIST PAGE 1 lo 83

92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION (CONTINUED)
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
0: FOR FAST REACTORSc
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
92 URANIUM 239 NEUTRON FISSION CROSS SECTION
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
M: NEW REQUESTc
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
A: ENERGY RESOLUTION - 3 PERCENTo
661646 loOO MEV 15o 0 MEV loOX 2 USA GoEoHANSEN LAS
O: RATIO TO U-235 FISSION WANTEDo
A: ENERGY RESOLUTION - 3 PERCENTo
FISSION LIST PAGE 1 lo 83

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
M: SUBSTANTIAL MODIFICATIONSo
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
94 PLUTONIUM 237 NEUTRON FISSICN CROSS SECTION
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
O: FOR FAST REACTOR CALCULATIONSo
FISSION LIST PAGE IIo 84

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
0: FOR FAST REACTOR CALCULATIONSo
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
M: NEW REOUESTO
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
0: FOR CRITICAL ASSEMBLIESc
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,
PRIORITY 2 ACCURACY 15 PERCENTc
FROM 1o 4 - 2c 5 MEV ACCURACY 17 PERCENT,
PRIORITY 2 ACCURACY 17 PERCENTo
FROM 2o 5 - So 0 MEV ACCURACY 3? PERCENT.
PRIORITY 2 ACCURACY 3C PERCENTo
0: NEED FOR FAST REACTOR CALCULATIONo
FOR MORE DETAIL SEE INTRODUCTIONo
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
FOR FAST REACTORSc
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
CROSS SECTION FOR INELASTIC REMOVAL BELOW FISSION
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
FISSION LIST PAGE I lo 85

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
O: FOR FAST REACTORSo
242035 1 So 0 MEV 20o0X 2 FR AoM1CHAUDON BRC
0: FOR CRITICAL ASSEMBLIESc
94 PLUTONIUM 239 NEUTRON NON-ELASTIC CROSS SECTION
652562 ICOo KEV 1Oo 0 MEV lOoOX 2 BAN Mo Me ISLAM RAM
0: FOR FAST REACTORSo
94 PLUTONIUM 239 NEUTRON CAPTURE CROSS SECTION
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
0: FOR FAST REACTORSc
202033 lo 00 KEV 200o KEV 5oOX 1
JAP SoKATSURAGI JAE
O: ALPHA ALSO USEFULc
0: FOR FAST REACTORSc
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
0: FOR CRITICAL ASSEMBLIESo
254012 SoOO KEV 1 Oo 0 MEV 1
CCP LoNoUSACHEV FEI
A: FROM Oc 5 - 100 KEV ACCURACY 4o5 PERCENT,
PRIORITY 2 ACCURACY 3o 7 PERCENTo
FROM Oc1 - Oc 8 MEV ACCURACY 10 PERCENT,
PRIORITY 2 ACCURACY 10 PERCENTo
FROM 0 o 8 - 4o 5 MEV ACCURACY SO PERCENT,
PRIORITY 2 ACCURACY 50 PERCENTo
ABOVE 4o 5 MEV REQUIREMENTS 2 TIMES WEAKERo
0: NEED FOR FAST REACTOR CALCULATIONSc
FOR MORE DETAIL SEE INTROOLCTIONo
M: NEW REQUESTc
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
A: LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGY AND
PHOTON SPECTRUMc
O: FOR STUDY OF ACTIVATION AND HEAT RELEASE IN COREc
242056 loOO KEV ISoC MEV lOoOX 1 FR Ao MICHAUDON BRC
0: FOR SHIELOINGo
94 PLUTONIUM 239 NEUTRCN N.2N
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
94 PLUTONIUM 239 NEUTRCN N.3N
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
94 PLUTONIUM 239 NEUTRON FISSICN CROSS SECTION
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
CALIBRATION 1 PERCENTo
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
FOR FAST REACTOR CALCULATIONSo
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
A: ACCURACY FOR AVERAGE VALUE OF THE ERROR BETWEEN
E AND 2EC
o: FOR FAST REACTORSO
M: MODIFIED (PARTIALLY FULFILLEDLO
693076 2So 3 MV 15o 0 MEV MoMoISLAM RAM
FOR FAST REACTORSc
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
FIRST PRIORITY BECAUSE IT IS DIFFICULT TO
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
SUBSTANTIAL MODIFICATIONSo
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
CALIBRATION 1 PERCENTo
241125 1Oo 0 KEV lo 00 MEV
BoHUTCHINS
0: RATIO TO U-235 (N.F) WANTEDo
M: NEW REQUESTo
242606 lo 00 KEV 5o00 MEV SWC Ho HAEGGBLOM
A: ACCURACY 2 PERCENT TO 1 MEV,
0: FAST REACTOR CALCULATIONSo
5 PERCENT ABOVEo
242635 1 So 0 MEV AoMICHAUDON BRC
A: ACCURACY 5 PERCENT TO 1 KEV. 2 PERCENT ABOVEo
0: FOR CRITICAL ASSEMBLIES,
FISSION LIST PAGE IIo 87

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,
PRIORITY 2 ACCURACY lo2 PERCENTo
FROM Oc1 - 0 c 8 MEV ACCURACY 3o0 PERCENT.
PRIORITY 2 ACCURACY lo3 PERCENTo
FROM OoS - 4o 5 MEV ACCURACY 4o 0 PERCENT,
PRIORITY 2 ACCURACY 2o6 PERCENTo
ABOVE 4c5 MEV REQUIREMENTS 2 TIMES WEAKERo
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTIONo
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
FOR FAST REACTOR CALCULATIONSo
Z12DZe 2 Oo 0 KEV 1 OOo KEV lOcOX 3 UK Co'Go CAMPBELL
A: ACCURACY FOR AVERAGE VALUE OF THE ERROR BETWEEN
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
FIRST PRIORITY BECAUSE IT IS DIFFICULT TO
INTERPRET THE SELF-SHIELDING FACTORS FROM
MACROSCOPIC DATA ONLYc
SUBSTANTIAL MODIFICATIONSo
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,
0: FOR CRITICAL ASSEMBLIESo
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,
PRIORITY 2 ACCURACY 102 PERCENTo
ABOVE 4,5 MEV REQUIREMENTS 2 TIMES WEAKERo
NEED FOR FAST REACTOR CALCULATIONSc
FOR MORE DETAIL SEE INTRODUCTIONo
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
0: FOR FAST REACTORSo
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
FISSION LIST PAGE IIo 126

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
O: FOR FAST REACTORSc
242103 15o0 MEV loOX 1 FR AoMICHAUDON BRC
0: FOR CRITICAL ASSEMBLIESc
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
FOR CALCULATION OF FISSION PRODUCT POISONSo
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
0: FOR CALCULATION OF FISSION PRODUCT POISONSo
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
M: NEW REQUESTo
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
0: FOR THERMAL REACTORSo
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
0: NEEDED FOR FAST REACTOR CALCULATIONSo
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,
M: SUBSTANTIAL MODIFICATIONSo
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
O: FOR FAST REACTORSc
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
O: FOR FAST REACTORSc
M: SUBSTANTIAL MODIFICATIONSo
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
o: FOR FAST REACTOR CALCULATIONSo
MOST RECENT RESULTS ARE DISCREPANT,
652452 lo 00 KEV 500o KEV lOoOX 2 SWC Ho HAEGGBLOM AE
A: ENERGY DEPENDANCE WITHIN 10 PERCENTo
0: NEEDED FOR FAST REACTOR CALCULATIONSo
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
O: SEE GENERAL COMMENTS IN THE INTRODUCTION
M: SUBSTANTIAL MODIFICATIONSo
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,
PRIORITY 2 ACCURACY 14 PERCENTo
FROM 0,8 - 4,5 MEV ACCURACY 46 PERCENT.
PRIORITY 2 ACCURACY 46 PERCENTo
ABOVE 4o5 MEV REQUIREMENTS 2 TIMES WEAKERo
o: NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTIONo
M: NEW REQUESTo
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,
FISSION LIST PAGE II, 91

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
A: LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGY AND
PHOTON SPECTRUMo
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
SEE GENERAL COMMENTS IN THE INTRODUCTION
SUBSTANTIAL MOO IFICATIONSo
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
FOR FAST REACTOR CALCULATIONSo
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
A: ACCURACY OF 5 PERCENT USEFULo
232008 5o 00 MEV lOoOX HoHAEGGBLOM AE
FAST REACTOR CALCULATIONSo
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
FOR CRITICAL ASSEMBLIESc
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
ABOVE 4o5 MEV REQUIREMENTS 2 TIMES WEAKERo
NEED FOR FAST REACTOR CALCULATIONSo
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
O: FOR FAST REACTORSc
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
O: SEE GENERAL COMMENTS IN THE INTRODUCTION
M: SUBSTANTIAL MODIFICATIONSo
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,
PRIORITY 2 ACCURACY 3o0 PERCENTo
FROM Oo 8 - 4o 5 MEV ACCURACY 20 3 PERCENT,
PRIORITY 2 ACCURACY 2o0 PERCENTo
ABOVE 4o5 MEV REQUIREMENTS 2 TIMES WEAKERo
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTION
NEW REQUESTo
FISSION LIST PAGE I Io 107

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©
M: SUBSTANTIAL MODIFICATIONSo
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
A: ACCURACY FOR AVERAGE VALUE OF THE ERROR BETWEEN
E AND 2Ec
O: FOR THERMAL REACTORSo
Z12Q9£ 1.00 KEV 2© 00 KEV 2 0 e 0 X Jo Go TYROR WIN
A: ACCURACY FOR AVERAGE VALUE OF THE ERROR BETWEEN
E AND 2Eo
0: FOR THERMAL REACTORSo
94 PLUTONIUM 241 NEUTRON CAPTURE CROSS SECTION
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
O: FAST REACTOR CALCULATIONSo
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,
ACCURACY 30 PERCENTo
4 o 5 MEV ACCURACY 50 PERCENT,
ACCURACY 50 PERCENTo
ABOVE 4o 5 MEV REQUIREMENTS 2 TIMES WEAKER©
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTION
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
FISSION LIST PAGE II, 93

94 PLUTONIUM 241 TOTAL PHOTON PRODUCTION CROSS SECTION
652460 120c KEV 20o0X CoGoCAMPBELL WIN
Q: GAMMA SPECTRUM WANTEDo
A: LOW RESOLUTION ADEQUATE FOR INCIDENT ENERGY AND
PHOTON SPECTRUMo
0: FOR STUDY OF ACTIVATION AND HEAT RELEASE IN COREo
94 PLUTONIUM 241 NEUTRON FISSION CROSS SECTION
661S5S 1 So 0 MEV loOX Go EcHANSEN LAS
Q: RATIO TO U-235 FISSION WANTEDc
A: ENERGY RESOLUTION - 3 PERCENTo
662022 1 Oo 0 KEV 1 5o 0 MEV lOoOX P ScKATSURAGI JAE
O: RESONANCE PARAMETERS ALSO REQUIREDo
O: FOR FAST REACTORo
M: SUBSTANTIAL MODIFICATIONSO
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
A: ACCURACY FOR AVERAGE VALUE OF THE ERROR BETWEEN
E AND 2Ec
0: FOR FAST REACTORSc
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,
PRIORITY 2 ACCURACY 5c0 PERCENTo
FROM 0o8 - 4o5 MEV ACCURACY 10 PERCENT.
PRIORITY 2 ACCURACY 9c7 PERCENTo
ABOVE 4o5 MEV REQUIREMENTS 2 TIMES WEAKERo
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTIONo
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
M: SUBSTANTIAL MODIFICATIONSo
652465 lOOo EV 1 o 00 MEV 20o0X CoGoCAMPBELL WIN
A: ACCURACY FOR AVERAGE VALUE OF THE ERROR BETWEEN
E AND 2Eo
O: FOR FAST REACTORSo
Zfl2042 2So 3 MV 1 o OX HoTELLIER SAC
O: EVALUATION MAY SUFFICE IF IT EXPLAINS
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
0: FOR FAST REACTOR CALCULATIONSo
FISSION LIST PAGE I Io 107

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
0: FOR THERMAL REACTORSo
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
M: SUBSTANTIAL MODIFICATIONS,
632466 1o 00 KEV 1 So 0 MEV SoOX 2 GER BoGOEL KFK
721095 1o 00 MEV lOoO MEV 6oOX 1 USA CoEcTILL ANL
M: SUBSTANTIAL MODIFICATIONSo
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.
PRIORITY 2 ACCURACY 4o 0 PERCENTo
ABOVE 4,5 MEV REQUIREMENTS 2.TIMES WEAKER,
O: NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTION
M: NEW REQUESTc
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,
94 PLUTONIUM 242 NEUTRON CAPTURE CROSS SECTION
Z02S47 2 5,3 MV HoTELLIER SAC
0: EVALUATION MAY SUFFICE IF IT EXPLAINS
0ISCREPANCIESO
Z02046 5,00 KEV He TELL IER SAC
A: ACCURACY FOR RATIO TO THERMAL CROSS SECTIONo
0: EVALUATION MAY SUFFICE IF IT EXPLAINS
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
0: FOR FAST REACTOR CALCULATIONSo
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,
ACCURACY 30 PERCENTo
Oo 8 MEV ACCURACY 30 PERCENT,
ACCURACY 30 PERCENTc
4c S MEV ACCURACY SC PERCENT,
ACCURACY 50 PERCENTo
ABOVE 4o5 MEV REQUIREMENTS 2 TIMES WEAKERo
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTION
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
94 PLUTONIUM 242 NEUTRCN FISSICN CROSS SECTION
742005 1o 00 KE V 5o00 MEV 1 Oo OX SWC Ho HAEGGBLOM AE
O: FAST REACTOR CALCULATIONSo
94 PLUTONIUM 242 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR)
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
O: FOR FAST REACTOR CALCULATIONSo
94 PLUTONIUM 243 NEUTRON CAPTURE CROSS SECTION
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
M: NEW REQUESTo
-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
94 PLUTONIUM 243 NEUTRON FISSICN CROSS SECTION
252025 500c KEV lOoOX RoYUMOTO
HoMATSUNOBU
PNC
SAE
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
NEW REQUESTo
252030
2« 00 MEV lOoO MEV lOoOX RoYUMOTO
HoMATSUNOBU
PNC
SAE
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
FISSION LIST PAGE IIo 96

94 PLUTONIUM 245 NEUTRCN FISSICN CROSS SECTION
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
FOR FAST REACTORSc
WIN
Z12110 500o EV 1o 00 MEV lOoOX 2 FR
JoYoBARRE
CAD
o:
o:
RELATIVE TO U-236 CAPTUREc •
FOR FAST REACTOR CALCULATIONSo
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:
FOR CRITICAL ASSEMBLIESc
232032 lOoO MV 1 OOo MV 1 JAP
RoYUMOTO
HoMATSUNOBU
PNC
SAE
0: ENERGY DEPENDENCE WANTEDo
A: ACCURACY REQUIRED 5 TO 10 PERCENTo
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REOUESTc
FISSION LIST PAGE I Io 107

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
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REOUESTc
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
0: FOR FAST REACTOR CALCULATIONSo
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-
0: FOR CRITICAL ASSEMBLIESo
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
FOR FAST REACTOR CALCULATIONSo
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.
SUBSTANTIAL MODIFICATIONSo
211663 2 5.3 MV 2 CAN
WoH.WALKER
CRC
o:
A:
FOR 16 HOUR ISOMERo
ACCURACY REQUIRED 500 Bo
UNKNOWN CROSS SECTIONo
FISSION LIST PAGE IIo 96

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
FOR FAST REACTOR CALCULATIONSo
252035 25o3 MV 1 Oo 0 MEV RoYUMOTO
HoMATSUNOBU
PNC
SAE
O: WANTED FOR GROUND AND ISOMERIC STATE So
A: ACCURACY REQUIRED 5 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
M: NEW REQUESTo
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
95 AMERICIUM 242 NEUTRON FISSION CROSS SECTION
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
M: SUBSTANTIAL MODIFICATIONSo
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,
A: ACCURACY REQUIRED 10 TO 20 PERCENTo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
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
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
FOR FAST REACTOR CALCULATIONSo
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
O: FOR FAST REACTOR CALCULATIONSo
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
SUBSTANTIAL MODIFICATIONSo
FISSION LIST PAGE I Io 101

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
M: NEW REQUESTO
762636 1 Oo 0 MEV
RoYUMOTO
HoMATSUNOBU
PNC
SAE
Q: PRODUCTION OF AM-244 AND AM-244 M WANTEOo
A: ACCURACY REQUIRED 5 TO 20 PERCENTo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUEST;
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
95 AMERICIUM 243 NEUTRON FISSION CROSS SECTION
712111 15o 0 MEV JoYo EARRE
0: RELATIVE TO U-235 FISSIONo
0: FOR FAST REACTOR CALCULATIONSo
75233-7 1 Oo 0 MEV
RoYUMOTO
HoMATSUNOBU
PNC
SAE
A: ACCURACY REQUIRED 10 TO 20 PERCENTo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTC
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
0: FOR FAST REACTOR CALCULATIONSo
95 AMERICIUM 243 NEUTRCN ABSORPTION RESONANCE INTEGRAL
712.114 1 Oo OX 2 FR HoTELLIER SAC
95 AMERICIUM 244 NEUTRCN CAPTURE CROSS SECTION
25204C 25o 3 MV 1 Oo 0 MEV 2 JAP RoYUMOTO PNC
HoMATSUNOBU
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
M: NEW REQUESTo
95 AMERICIUM 244 NEUTRON FISSICN CROSS SECTION
75263S 2 5o 3 MV 1Oo 0 MEV 2 JAP Ro YUMOTO PNC
HoMATSUNOBU
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
M: NEW REQUESTC
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
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
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
0: FOR FAST REACTOR CALCULATIONSc
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
A: ACCURACY REQUIRED 10 TO 20 PERCENTo
o: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTC
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: VALUE RELATIVE TO CF-252 NUo
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
M: SUBSTANTIAL MODIFICATIONSo
96 CURIUM 243 NEUTRON CAPTURE CROSS SECTION
211532 2 So 3 MV Wo He WALKER
A: ACCURACY REQUIRED 50 Be
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,
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
FISSION LIST PAGE I Io 101

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
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTo
-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
0: ENERGY DEPENDENCE WANTEDo
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
Z52DA4
2 Oo 0 E V
1 OOo
lOoOX
RoYUMOTO
HoMATSUNOBU
PNC
SAE
o: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTo
2S20A5
3o 00
MEV
1Oo 0
MEV
RcYUMOTO
HoMATSUNOBU
PNC
SAE
A: ACCURACY REQUIRED 10 TO 20 PERCENTo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
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
96 CURIUM 244 NEUTRCN CAPTURE CROSS SECTION
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
M: SUBSTANTIAL MODIFICATIONSO
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
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
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
0: FOR FAST REACTOR CALCULATIONSo
Z52fl»fl 1 o 00 KEV lOoO KEV RoYUMOTO
HoMATSUNOBU
PNC
SAE
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
0: VALUE RELATIVE TO CF-252 NUo
0: FOR FAST REACTOR CALCULATIONSc
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
M: SUBSTANTIAL MODIFICATIONSo
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
SUBSTANTIAL MODIFICATIONSo
222052 1 OoO MV loOO EV lOoOX RoYUMOTO
HoMATSUNOBU
PNC
SAE
0: ENERGY DEPENDENCE WANTEDo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REOUESTO
252054
6 Oo 0 E V 1 Oo 0 MEV 20o 0 X RoYUMOTO
HoMATSUNOBU
PNC
SAE
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
A: NEED 10 PERCENT IN RESONANCE INTEGRALo
NEED INTEGRAL ALPHA TO 10 PERCENTo
0: TO EVALUATE CF PRODUCTIONo
M: SUBSTANTIAL MODIFICATIONSo
252050 lOoO MV
1 o 00 EV
JAP
RoYUMOTO
HoMATSUNOBU
PNC
SAE
0: ENERGY DEPENDENCE WANTEDo
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REOUESTc
ZS2051 60o0 EV
1 Oo 0 KEV
JAP
RoYUMOTO
HoMATSUNOBU
PNC
SAE
A: ACCURACY REQUIRED 5 TO 10 PERCENTo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REOUESTo
Z52052 3o 00 MEV lOoO MEV JAP RoYUMOTO
HoMATSUNOBU
PNC
SAE
A: ACCURACY REQUIRED 10 TO 20 PERCENT®
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUEL*
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTo
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
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REOUESTc
75205S
4 OOo EV 1 Oo 0 MEV RoYUMOTO
HoMATSUNOBU
PNC
SAE
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
0: ENERGY DEPENDENCE WANTEDo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
752055 1 o 00 KEV
1 Oo 0 KEV
RoYUMOTO
HoMATSUNOBU
PNC
SAE
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
NEW REQUESTc
752057 3o 00 MEV 1Oo 0 MEV 20oGX RoYUMOTO
HoMATSUNOBU
PNC
SAE
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
0: SHAPE OF THERMAL CROSS SECTION ESPECIALLY
IMPORTANT;
A: NEED 20 PERCENT IN RESONANCE INTEGRALo
O: TO EVALUATE CF PRODUCTIONo
M: SUBSTANTIAL MODIFICATIONSo
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
o: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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;
M: SUBSTANTIAL MODIFICATIONSo
252060 2So 3 MV
20o 0
EV
RcYUMOTO
HoMATSUNOBU
PNC
SAE
0: ENERGY DEPENDENCE WANTEDo
A: ACCURACY REQUIRED 5 TO 10 PERCENT,
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REOUESTc
252061 6 Oo 0 E V
lOoO
KEV
RcYUMOTO
HoMATSUNOBU
PNC
SAE
A: ACCURACY REQUIRED 5 TO 10 PERCENTo
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
252062 3o 00 MEV lOoO MEV
Ro 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 FUELc
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
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
96 CURIUM 248 NEUTRCN CAPTURE CROSS SECTION
252562 25o3 MV 1Oo 0 MEV 1 JAP Rc YUMOTO PNC
HoMATSUNOBU
SAE
A: ACCURACY REQUIRED 1C 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
M: NEW REQUESTc
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
FISSION LIST PAGE I lo 105

97 BERKELIUM 249 NEUTRON CAPTURE CROSS SECTION
631-254 LOCO KEV FoJoMC CROSSON SRL
0: SHAPE OF THERMAL CROSS SECTION ESPECIALLY
IMPORTANTo
A: 10 PERCENT THERMAL AND RESONANCE INTEGRALo
O: FOR CF PRODUCTIONO
M: SUBSTANTIAL MODIFICATIONS,
252624 2 So 3 MV 1 Oo 0 MEV 20o0X 1 JAP RoYUMOTO PNC
HoMATSUNOBU
SAE
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTO
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
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
NEW REQUESTc
752672
5o 00
MEV
1Oo 0
MEV
20 oO X
Rc YUMOTO
HoMATSUNOBU
PNC
SAE
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTo
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
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTo
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
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
FISSION LIST PAGE I Io 107

9 8 CAL IFOSMIUM 2EC CAPTURE CROSS SECTION
651551 2So 3 MV lOoO KEV ICoOX A Fo Jc MC CROSSON SRL
A: NEED 10 PERCENT IN RESONANCE INTEGRALo
0: TO EVALUATE CF PRODUCTION
252025 2 So 3 MV I Oo 0 MEV 1 JAP RoYUMOTO PNC
HoMATSUNOBU
SAE
A: ACCURACY REQUIRED 10 TO 20 PERCENTo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTC
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
A: ACCURACY 10 PERCENT IN RESONANCE INTEGRALo
0: TO EVALUATE CF PRODUCTION
252028 2 5o 3 MV 1Oo C MEV 20oCX 2 JAP RoYUMOTO PNC
HoMATSUNOBU
SAE
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
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
A: ACCURACY 10 PERCENT IN RESONANCE INTEGRALo
0: TO EVALUATE CF PRODUCTION
752081 2503 MV 1Oo 0 MEV 1 JAP RoYUMOTO PNC
HoMATSUNOBU
SAE
A: ACCURACY REQUIRED 10 TO 20 PERCENTo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTC
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
0: TO EVALUATE CF PRODUCTIONo
M: NEW REQUESTo
752060
1 Oo 0 MEV
RoYUMOTO
HoMATSUNOBU
PNC
SAE
A: ACCURACY REQUIRED 10 TO 20 PERCENTo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTC
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
A: ACCURACY OF 1 PERCENT USEFULo
o: FOR USE AS STANDARDo
M: SUBSTANTIAL MODIFICATIONSo
212115 PoRIBON SAC
o: DISCREPANCY BETWEEN DIFFERENTIAL AND MAXWELL
SPECTRUM EXPERIMENTS HAVE TO BE RESOLVED
FOR 2200M/S DATAo
FISSION LIST PAGE I lo 108

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
FIRST PRIORITY BECAUSE IT IS DIFFICULT TO
RECONCILE THIS STANDARD WITH MACROSCOPIC
EXPERIMENTS; '
SUBSTANTIAL MODIFICATIONSo
241130 0o25X
A RoEHRLICH KAP
A: ACCURACY 1 PERCENT OR BETTER USEFULo
o: FOR USE AS A STANDARDo
M: NEW REOUESTo
-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
M: NEW REQUESTo
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
A: ACCURACY 10 PERCENT IN RESONANCE INTEGRALo
0: TO EVALUATE CF PRODUCTIONo
152034 2 5o 3 MV 1 Oo 0 MEV JAP
RoYUMOTO
HoMATSUNOBU
PNC
SAE
A: ACCURACY REQUIRED 10 TO 20 PERCENTo
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
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
FISSION LIST PAGE I Io 109

98 CALIFORNIUM 252 NEUTRCN FISSICN CROSS SECTION
252062 2So 3 MV
20o 0 EV lOoOX
RoYUMOTO
HoMATSUNOBU
PNC
SAE
O: ENERGY DEPENDENCE WANTEDo
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REOUESTo
252062 So 00 MEV
1Oo 0 MEV 20o0X
RoYUMOTO
HoMATSUNOBU
PNC
SAE
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
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
M: NEW REQUESTo
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
A: ACCURACY REQUIRED 10 TO 20 PERCENTo
o: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTc
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
O: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
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
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo
M: NEW REQUESTO
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 LIST PAGE IIo 106

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,
PRIORITY 2 ACCURACY 13 PERCENTo
FROM 1o 4 - 2o 5 MEV ACCURACY 15 PERCENT,
PRIORITY 2 ACCURACY IS PERCENTo
FROM 2c 5 - SoO MEV ACCURACY 30 PERCENT.
PRIORITY 2 ACCURACY 30 PERCENTo
0: NEED FOR FAST REACTOR CALCULATIONo
FOR MORE DETAIL SEE INTRODUCTIONo
M: NEW REOUESTc
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,
PRIORITY 2 ACCURACY 7 PERCENTo
FROM Oo1 - Oc 8 MEV ACCURACY 15 PERCENT,
PRIORITY 2 ACCURACY 14 PERCENTo
FROM O08 - 4o 5 MEV ACCURACY 48 PERCENT,
PRIORITY 2 ACCURACY 48 PERCENTo
ABOVE 4o5 MEV REQUIREMENTS 2 TIMES WEAKERo
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTION
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
0: FOR THERMAL REACTORSo
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
M: SUBSTANTIAL MODIFICATIONSO
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,
NEED FOR FAST REACTOR CALCULATIONSo
FOR MORE DETAIL SEE INTRODUCTIONo
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.
Priority Criteria
.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
Priority 3 shall be assigned to nuclear data which
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
Priority 4 shall be assigned to nuclear data which
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
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O 0 0 oooooooooooo
ooooooooooooooo
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o o o o o o o o o o o o o o o
ooooooooooooooo
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
M: NEW REQUESTo
1 HYDROGEN 3 NIUTRCN N.2N
112295 15o 0 MEV 2 FR AoMICHAUDON BRC
A: ACCURACY. REQUIRED TO BETTER THAN 20 PERCENTo
M: NEW REQUESTo
2 ~ HELIUM 3 NEUTRON N.F
2-£25Sf 1o 00 KEV 15o 0 MEV lOoOX 1 FR AoMICHAUDON BRC
M: NEW REQUESTo
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
M: NEW REQUESTO
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
M: SUBSTANTIAL MODIFICATIONSo
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
M: NEW REQUESTo
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
M: NEW REQUESTo
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
M: NEW REQUESTo
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
M: NEW REQUESTo
STATUS : STATUS
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
M: NEW REOUESTo
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
M: SUBSTANTIAL MODIFICATIONSo
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
M: NEW REQUEST,
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
O: GAMMA RAY HEATING AND SHIELDING CALCULATIONSo
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,
MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo
M: NEW REQUESTo
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
M: NEW REQUESTo
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
M: SUBSTANTIAL MODIFICATIONSo
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
M: NEW REQUESTo
FUSION LIST PAGE IIIo 4

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
MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo
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,
MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo
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
M: NEW REQUEST,
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,
M: NEW REQUESTo
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,
M: NEW REQUESTo
FUSION LIST PAGE IIIo 5

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
M: NEW REQUESTO
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
M: NEW REQUESTO
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
M: NEW REQUESTo
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
M: SUBSTANTIAL MODIFICATIONSo
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
0: CALCULATION OF HEAT GENERATION AND SHIELDING
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
M: SUBSTANTIAL MODIFICATIONSo
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
0: CALCULATION OF HEAT GENERATION AND SHIELDING
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
M: SUBSTANTIAL MODIFICATIONSo
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
MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo
M: NEW REOUESTo
9 FLUORINE 19 TOTAL PROTON PRODUCTION CROSS SECTION
ZA126S ISoO MEV FoGoPEREY
0: CALCULATION OF HYDROGEN PRODUCTIONo
M: NEW REOUESTo
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
M: NEW REOUESTo
13 ALUMINUM 27
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
M: NEW REQUESTo
13~ALUMTNUM~27~ * NEUTRON
DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION
ZS126S 1 4o 0 MEV USA PoGoYOUNG LAS
Q: SPECTRA AT SEVERAL ANGLES REQUIREDo
MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo
M: NEW REQUESTo
13 ALUMINUM 27
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
UNCERTAINTY FILES REQUIRED TO PERFORM CROSS
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
M: NEW REQUESTo
FUSION LIST PAGE IIIo 7

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
M: NEW REOUESTo
13 ALUMINUM 27 NEUTRON TOTAL ALPHA PRODUCT ION CROsi IECTION
2£U22& 1 SoO MEV ISoOX 2 USA RoHAIGHT
0: HELIUM PRODUCTION REQUIREOo
M: NEW REOUESTo
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
UNCERTAINTY FILES REQUIRED TO PERFORM CROSS
SECTION SENSITIVITY ANALYSIS FOR FUSION DEVlCESo
M: NEW REQUESTo
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
M: NEW REQUESTo
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
M: NEW REQUESTo
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
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo
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
M: NEW REOUESTo
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
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
SENSITIVITY ANALYSIS FOR NEAR-TERM FUSION
OEVICESo
M: NEW REQUESTo
24 CHROMIUM TOTAL PHOTON PRODUCTION CROSS SECTION
241230 1 o 00 KEV 20 o 0 MEV 20o0X 2 USA MoBhAT
M: NEW REQUESTo
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
O: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
24 CHROMIUM* DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION
lilZZl 14o0 MEV
1 SoOX USA RoHAIGHT LRL
Q: SPECTRA AT SEVERAL ANGLES REQUIREDo
M: NEW REQUESTo
24 CHROMIUM 'NEUTFCN -
2220XS 14o 0 MEV lOoOX FR DoBRETON FAR
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
M: NEW REQUESTo
24 CHROMIUM NEUTRCN
2£202£ 14e0 MEV 10.OX 3 FR .Oo BRETON FAR
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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.
M: NEW REQUESTo
FUSION LIST PAGE IIlo 10

24 CHROMIUM 52
20o0 MEV 25o OX USA M,BHAT BNL
O: NEEDED FOR EVALUATIONo
M: NEW REOUESTo
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©
M: NEW REOUESTo
2 5 MANGANESE 55 NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION
241232 I o OO KEV 20,0 MEV 20o0X USA M,BHAT
M: NEW REQUEST,
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
M: NEW REQUEST,
Z&lZSt 15,0 MEV 15,OX 2 USA RoHAIGHT LRL
Q: EVALUATION REQUESTEDo
0: NEEDED FOR FERF DESIGN,
M: NEW REQUEST,
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
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
M: NEW REQUEST,
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,
NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION
132120 1 5o 0 MEV RoHANCOX HAR
0: ENERGY AND ANGULAR DISTRIBUTION OF GAMMA RAYS
WANTEDo
M: NEW REQUEST,
FUSION LIST PAGE IIIo 11

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
132022 14o 0 MEV lOoOX 2 FR DoBRETON FAR
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
M: NEW REOUESTO
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
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
M: NEW REOUESTO
IA129Q ISoO MEV 1 So OX 2 , US A RoHAIGHT LRL
0: HELIUM PRODUCTION REQUIREDo
M: NEW REOUESTo
26~IRON 54 " SIUTRCN NTF ~
J41231 15o 0 MEV
0: PRODUCTION OF MN-54o
M: NEW REQUESTo
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
M: NEW REQUESTO
STATUS—
STATUS
RPI HOCKENBURY* - AiSNDC-3 155(1972) . WORK IN PROGRESS Oo 1 TO 200 KEVo
KFK BEER* - EANCC(H)-157 (1973), EXPERIMENT PLANNEOo
FUSION LIST PAGE IIIo 12

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
SENSITIVITY ANALYSIS FOR NEAR-TERM FUSION
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
M: NEW REQUESTo
-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
M: NEW REQUESTo
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
SENSITIVITY ANALYSIS FOR NEAR-TERM FUSION
DEVlCESo
M: NEW REQUESTo
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
SENSITIVITY ANALYSIS FOR NEAR-TERM FUSION
DEVlCESo
M: NEW REQUESTO
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
o: GAMMA RAY HEATING AND SHIELDING CALCULATIONSo
1o 00 MEV 15o 0 MEV A VoJoORPHAN SAI
O: EVALUATION ONLY TO INCORPORATE NEW DATAo
0: FOR CALCULATING GAMMA-RAY HEATING IN COILSo
M: NEW REQUESTo
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
M: NEW REQUESTo
FUSICN LIST PAGE IIIo 14

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,
M: NEW REQUESTo
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,
M: NEW REQUESTo
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,
M: NEW REQUEST,
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
o: GAMMA RAY HEATING AND SHIELDING CALCULATIONSo
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,
M: NEW REQUEST,
* NCHOEANESXEOEOEAEEOEE E*•AENEOE•BE*EEHEAA*EOHONBOEONGAHHAHAHO»HE EA AEOEOEOMGC»O=EAOOOC^C33EBBSAOEABOSAEEOCR
FUSICN LIST PAGE IIIo 16

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
MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo
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
M: NEW REOUESTo
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
M: NEW REOUESTo
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
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
o: GAMMA RAY HEATING AND SHIELDING CALCULATIONSo
FUSION LIST PAGE IIIo 17

42 MOLYBDENUM _ NEUTRON TOTALPHOTON PRODUCTIONCROSS SECTION (CONTINUED)
ZA1315 80 00 M£v 15.0 MEV 15.OX 3 USA FoGoPEREY ORL
M: NEW REQUEST.
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
O: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
TRANSMUTATION RATES AND RADIOACTIVE AFTERHEATo
12&&55 1 So 0 MEV ISoOX 1 CCP IoNoGOLOVIN KUR
O: HYDROGEN ACCUMULATION CALCULATIONSo
132531 14o 0 MEV lOoOX 3 FR DoBRETON FAR
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
Z9211.1 14o 0 MEV lOoOX 2 GER FoWELLER KFK
O: FOR RADIATION DAMAGE CALCULATIONSo
NO DATA AVAILABLEo
M: NEW REQUEST.
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
TRANSMUTATION RATES AND RADIOACTIVE AFTERHEATo
Z2465.6 15o 0 MEV ISoOX 1 CCP IONOGOLOVIN KUR
O: HELIUM ACCUMULATION CALCULATIONSo
ZJ2A22 14.0 MEV lOoOX 3 FR DoBRETON FAR
O: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
M: NEW REQUEST.
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
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
FUSION LIST PAGE IIIo 18

74 TUNGSTEN KEUTRCK N.2N
2S2SM 14o 0 MEV lOoOX 3 FR DoBRETON FAR
O: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
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
0: POTENTIAL CONSTITUENT OF CONTAINMENT VESSELo
STA TUS
STATUS
JUL OAI Mo - NF/A 242 317(1574). CATA AT 14o7 MEV FOR ENRICHED ISOTOPESo
74~TUNGSTEN *" NEUTRON S7ALPHA
222232 14o 0 MEV lOoOX 3 FR DoBRETON FAR
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
SENSITIVITY ANALYSIS FOR NEAR-TERM FUSION
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
SENSITIVITY ANALYSIS FOR NEAR-TERM FUSION
DEVlCESo
M: NEW REOUESTo
NEUTRCN TOTAL PHOTON PRODUCTION CROSS SECTION
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
M: NEW REQUESTo
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
O: GAMMA RAY HEATING AND SHIELDING CALCULATIONSo
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.UM^ill
= ~ = = 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
0: POSSIBLE USE AS NEUTRON MULTIPLIERo
Z41J1J 1 So 0 MEV
o: EVALUATION REOUESTEOo
O: PRODUCTION OF U-237,
M: NEW REOUESTo
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
0: POSSIBLE USE AS NEUTRON MULTIPLIERo
ZA1.22fl 15o 0 MEV 1 5 oOX USA J oDo LEE LRL
0: EVALUATION REOUESTEDo
0: PRODUCTION OF U-236o
M: NEW REOUESTo
92 URANIUM 238 DOUBLE DIFFERENTIAL NEUTRON-EMISSION CROSS SECTION
ZA131S 1 4o 0 MEV 1 5o OX
0: SPECTRA AT SEVERAL ANGLES REOUIREOo
MUST RECORD NEUTRONS DOWN TO A FEW HUNDRED KEVo
M: NEW REOUESTo
FUSION LIST PAGE IIIo 20

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.
Priority Criteria
*
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
nuclear data that
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
nuclear data that
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,
M: NEW REQUESTc
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,
0: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASJJREMENTo
M: NEW REQUEST,
222003
NoSASAMOTO
JAE
Q: YIELD PER DISENTEGRATION OF 557 KEV GAMMA RAY
REQUIREDc
0: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENT,
M: NEW REQUEST,
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
FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
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
FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
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
FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENT
M: NEW REQUESTc
222012
loOX HoOKASHITA JAE
0: FOR 2c23 DAY ISOMERc
0: DIFFERENT VALUES ARE QUOTED IN THE LlTERATUREo
FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENTo
M: NEW REQUESTC
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
M: NEW REQUESTo
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
M: NEW REQUESTc
55 CESIUM 133 NEUTRON CAPTURE CROSS SECTION
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
Q: RESONANCE INTEGRAL ALSO WANTEDo
O: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENTo
M: NEW REQUESTC
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
FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
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
FISSION PRODUCT GAMMA RADIATIONo
222025 2 So 3 MV 3oOX 1 JAP He OKASHITA JAE
O: RESONANCE INTEGRAL ALSO WANTEDo
0: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENT,
M: NEW REOUESTo
STATUS
STATUS
SAC RIBONo - 7 3BOLCGNA 1 235. REVIEWo
55 CESIUM 137 NEUTRON CAPTURE CROSS SECTION
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
FISSION PRODUCT GAMMA RADIATIONo
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
FISSION PRODUCT GAMMA RADIATIONo
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
FISSION PRODUCT GAMMA RADIATIONo
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
M: NEW REQUESTo
222010 NcSASAMOTO JAE
a: YIELD PER DISINTEGRATION OF 432o 6 KEV GAMMA RAY
REOUIREDo
o: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENTo
M: NEW REQUESTc
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
FISSION PRODUCT GAMMA RADIATIONo
222511 HoOKASHITA JAE
0: YIELD PER DISINTEGRATION OF 133c5 KEV GAMMA RAY
REOUIREDo
0: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENTo
M: NEW REOUESTo
SAFEGUARDS LIST PAGE IVo 3

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
Q: RESONANCE INTEGRAL ALSO WANTEDo
0: FOR BURN UP CALCULATION FROM DESTRUCTIVE
MEASUREMENT-,
M: NEW REQUESTc
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

62 SAMARIUM 152 CAPTURE CROSS SECTION
Z22036 2 5o 3 MV
1 4o 0 MEV YoNAITO JAE
0: RESONANCE INTEGRAL ALSO WANTEDo
0: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENT,
M: NEW REQUESTc
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
o: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENTo
M: NEW REOUESTo
63 EUROPIUM 153 NEUTRON CAPTURE CROSS SECTION
722036 2 So 3 My
STA TUS-
STATUS-
1 4o 0 MEV HoOKASHITA JAE
0: RESONANCE INTEGRAL ALSO WANTEDo
0: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
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
FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENT,
M: NEW REQUESTc
STATUS
STATUS
ANL KARRAKER - PR £7 901 (1952)
ORL EMERY* - NSE 48 319(1972)
63 EUROPIUM 154 SPONTANEOUS TOTAL GAMMA RAY YIELD
722013 HoOKASHITA JAE
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
0: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE
MEASUREMENTo
M: NEW REOUESTc
92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION
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,
M: NEW REOUESTo
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
92 URANIUM 235 NEUTRON FISSION PRODUCT MASS YIELD SPECTRUM
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
222043 HoOKASHITA JAE
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
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND
NON-DESTRUCTIVE CALCULATIONSo
NEW REQUESTo
SAFEGUARDS LIST PAGE IVo 7

95 AMERICIUM 241
GAMMA
FISSICN PRODUCT MASS VI ELD SPECTRUM ( CONTINUED)
722051 HoOKASHITA JAE
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
NON-DESTRUCTIVE CALCULATIONSo
M: NEW REOUESTo
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
92 URANIUM 236 NEUTRON CAPTURE CROSS SECTION
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,
M: NEW REQUESTC
-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
92 URANIUM 238 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION
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,
92 URANIUM 238 NEUTRON FISSION PRODUCT MASS YIELD SPECTRUM
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
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND
NON-DESTRUCTIVE MEASUREMENTo
NEW REQUESTo
SAFEGUARDS LIST PAGE IV o 8

95 AMERICIUM 241
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),
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND
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
0: FOR BURN UP CALCULATIONSo
M: NEW REQUESTc
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,
M: NEW REQUESTo
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,
M: NEW REQUESTc
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
M: NEW REQUESTc
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,
M: NEW REQUESTc
SAFEGUARDS LIST PAGE IV o 9

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
M: NEW REQUEST;
Z 4115.4 loOX 2 USA No SC 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 SAFEGUARDSc
M: NEW REQUESTc
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
94 PLUTONIUM 238 NEUTRON CAPTURE CROSS SECTION
252566 2So 3 MV 1Oc 0 MEV lOoOX 2 GER Pc MCGRATH KFK
0: FOR BURN UP CALCULATIONSo
STA TUS
STATUS
LAS SILBERT* - LA.-5024 (1972) , CATA 18 EV TO 200 KEVo
KFK HINKELMANN - KFK-1186(1970). EVALUATION TO 10 MEVo
94 PLUTONIUM 238 NEUTRON FISSION CROSS SECTION
262565 1o 00 MEV lOoO MEV lOoOX 2 GER PoMCGRATH KFK
0: FOR BURN UP CALCULATIONSo
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
M: NEW REQUEST;
94 PLUTONIUM 239 NEUTRON CAPTURE CROSS SECTION
222041 25o 3 MV 14o 0 MEV 1 JAP YcNAITO JAE
A: ACCURACY REQUIRED AT THERMAL IS 3 PERCENT. 10
PERCENT ABOVEc
0: FOR BURN UP CALCULATION OF A PU LOADED THERMAL
REACTOR,
M: NEW REQUESTc
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
M: NEW REQUESTc
SAFEGUARDS LIST PAGE IVo 10

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,
0: FOR BURN UP CALCULATION OF A PU LOADED THERMAL
REACTOR,
M: NEW REOUESTc
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
94 PLUTONIUM 239 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR)
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
M: NEW REQUESTc
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-
94 PLUTONIUM 239 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION
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,
M: NEW REQUESTo
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
DATA WANTED FOR THERMAL NEUTRONS. FAST REACTOR
NEUTRONS(80-800 KEVI, FISSION SPECTRUM NEUTRONS
AND HIGH ENERGY NEUTRONS(14-15 MEVlc
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND
NON-DESTRUCTIVE CALCULATIONSo
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
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND
NON-DESTRUCTIVE CALCULATIONSc
NEW REQUESTc
Z22056 HcOKASHITA JAE
FISSION YIELD OF CS-134, PR-142 AND EU-154
WANTEDc
DATA WANTED FOR THERMAL NEUTRONS, FAST REACTOR
NEUTRONSC80-800 KEV), FISSION SPECTRUM NEUTRONS
AND HIGH ENERGY NEUTRONS(14-15 MEVlo
=OR BURN UP CALCULATION FROM DESTRUCTIVE AND
NON-DESTRUCTIVE CALCULATIONSo
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
94 PLUTONIUM 240 HALF LIFE
74-1138 A W,W-STROHM MNO
O: FOR ACCURATE CALORIMETRIC ASSAY OF PUo
M: NEW REQUESTo
94 PLUTONIUM 240 FISSION HALF LIFE
Z41144 A EoVoWEINSTOCK BNL
0: TO REDUCE ERRORS IN THE ASSAY OF HIGH-BURNUP PUc
M: NEW REQUEST;
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
SPONTANEOUS FISSION MEASUREMENTS OF PU IN
NUCLEAR MATERIALS SAFEGUARDSo
M: NEW REQUESTo
94 PLUTONIUM 240 SPONTANEOUS NEUTRONS EMITTED PER FISSION (NU BAR)
Z-41155 loOX 2 USA NoScBEYER ANL
A: ACCURACY 3-5 PERCENT USEFUL IN SHORT TERMo
0: FOR CALCULATION OF THE EFFECTIVE PU-240 FOR
SPONTANEOUS FISSION MEASUREMENTS OF PU IN
NUCLEAR MATERIALS SAFEGUARDSo
M: NEW REQUESTo
SAFEGUARDS LIST PAGE IVo 12

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
M: NEW REOUESTc
94 PLUTONIUM 240 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION
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
94 PLUTONIUM 241 HALF LIFE
Z4114S 1 o OX 2 USA WoW-.STROHM MNO
0: FOR ACCURATE CALORIMETRIC ASSAY OF PUo
M: NEW REQUESTo
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
94 PLUTONIUM 241 NEUTRON CAPTURE CROSS SECTION
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
A: ACCURACY REQUIRED AT THERMAL IS 2 PERCENT, 5
PERCENT ABOVEc
0: FOR BURN UP CALCULATION OF A PU LOADED THERMAL
REACTORo
M: NEW REQUESTo
94 PLUTONIUM 241 NEUTRON CAPTURE GAMMA RAY SPECTRUM
741140 25o3 MV 20o OX 2 USA Ro Ec WALTON LAS
Q: ABSOLUTE SPECTRA REQUlREDo
0: FOR DEVELOPMENT OF NONDESTRUCTIVE ASSAY METHODSo
M: NEW REQUESTc
SAFEGUARDS LIST PAGE IVc 13

94 PLUTONIUM 241 CAPTURE TO FISSION RATIO (ALPHA)
222047
14o 0 MEV YCNAITO JAE
A: ACCURACY REQUIRED AT THERMAL IS 1 PERCENT. 5
PERCENT ABOVEc
O: FOR BURN UP CALCULATION OF A PU LOADED THERMAL
REACTOR,
M: NEW REQUESTO
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,
94 PLUTONIUM 241 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION
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:
DATA WANTED FOR THERMAL NEUTRONS. FAST REACTOR
NEUT RON S(80-80C KEV). FISSION SPECTRUM NEUTRONS
AND HIGH ENERGY NEUTRONS(14—15 MEV)o
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND
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
DATA WANTED FOR THERMAL NEUTRONS, FAST REACTOR
NEUTRONS(80-800 KEV). FISSION SPECTRUM NEUTRONS
AND HIGH ENERGY NEUTRONS(14-15 MEV)0
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND
NON-DESTRUCTIVE CALCULATIONSo
NEW REQUEST,
222059 SOo OX 2 JAP HoOKASHITA JAE
0: FISSION YIELD OF CS-134, PR-142, AND EU-154
WANTED,
DATA WANTED FOR THERMAL NEUTRONS. FAST REACTOR
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
NON-DESTRUCTIVE CALCULATIONSo
M: NEW REQUEST,
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
A: ACCURACY 3-5 PERCENT USEFUL IN SHORT TERMo
O: FOR CALCULATION OF THE EFFECTIVE PU-240 FOR
SPONTANEOUS FISSION MEASUREMENTS OF PU IN
NUCLEAR MATERIALS SAFEGUARDSo.
M: NEW REQUESTo
SAFEGUARDS LIST PAGE IVo 14

94 PLUTONIUM 2 42 SPONTANEOUS NEUTRONS EMITTED PER FISSION (NU BAR)
Z4U55 NoS;BEYER ANL
A: ACCURACY 3-5 PERCENT USEFUL IN SHORT TERM,
O:- FOR CALCULATION OF THE EFFECTIVE PU-240 FOR
SPONTANEOUS FISSION MEASUREMENTS OF PU IN
NUCLEAR MATERIALS SAFEGUARDSo
M: NEW REQUESTc
94 PLUTONIUM 242 NEUTRON CAPTURE CROSS SECTION
722043 1 4o 0 MEV Yc NAITO JAE
A: ACCURACY REQUIRED AT THERMAL IS 5 PERCENT, 10
PERCENT ABOVEo
0: FOR BURN UP CALCULATION OF A PU LOADED THERMAL
REACTORo
M: NEW REQUESTc
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
M: NEW REQUESTo
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
94 PLUTONIUM 242 NEUTRON CAPTURE GAMMA RAY SPECTRUM
Z41141 25o 3 MV 20o OX A RoBcWALTON LAS
Q: ABSOLUTE SPECTRA REQUIREOo
0: FOR DEVELOPMENT OF NONDESTRUCTIVE ASSAY METHODSo
M: NEW REQUESTo
94 PLUTONIUM 242 NEUTRON FISSION CROSS SECTION
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
M: NEW REQUESTc
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
M: NEW REQUESTc
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
SAFEGUARDS LIST PAGE IVo 15

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
95 AMERICIUM 241 NEUTRON CAPTURE CROSS SECTION
762.061 2 5o 3 MV I Oo 0 MEV lOoOX GER PoMCGRATH KFK
0: FOR BURN UP CALCULATIONSo
M: SUBSTANTIAL MODIFICATIONSo
722544 25o 3 MV 1 4o 0 MEV JAP YoNAITO JAE
A: ACCURACY REQUIRED AT THERMAL IS 5 PERCENT, 10
PERCENT ABOVEo
0: FOR BURN UP CALCULATION OF A PU LOADED THERMAL
REACTORo
M: NEW REQUESTc
-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
M: NEW REQUESTo
95 AMERICIUM 241 FISSION CROSS SECTION
752060 20o 0 KEV 1 Oc 0 MEV PoMCGRATH
0: FOR BURN UP CALCULATIONSo
M: SUBSTANTIAL MODIFICATIONSo
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
95 AMERICIUM 242 NEUTRCN CAPTURE CROSS SECTION
722545 2So3 14c 0 MEV JAP YoNAITO JAE
A: ACCURACY REQUIRED AT THERMAL IS 10 PERCENT, 20
PERCENT ABOVEo
0: FOR BURN UP CALCULATION OF A PU LOADED THERMAL
REACTORo
M: NEW REQUESTo
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
M: NEW REQUESTc
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
M: NEW REQUESTc
LRL BROWNE+ - NCSAC-42 135(1971), IN PROGRESS TO 14 MEVc
LRL PERKINS* - NSE 32 131(1968). DATA FROM 0o4 EV TC 4o7 MEVc
SAFEGUARDS LIST PAGE IV o 16

95 AMERICIUM 243 NEUTRON CAPTURE CROSS SECTION
732132 25o3 MV lOoO MEV lOoOX 1 GER PoMCGRATH KFK
O: FOR PRODUCTION OF CM-244o
M: NEW REOUESTo
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
M: NEW REQUEST,
SAFEGUARDS LIST PAGE IVc 17

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
EUROPEAN-AMERICAN
EUROPEAN-AMERICAN
EUROPEAN-AMERICAN
GENERAL ATOMICS REPORTS
GULF RADIATION TECHNOLOGY
GULF RADIATION TECHNOLOGY
ISRAEL AEC REPORTS
IAEA TECHNICAL REPORTS
IDAHO NUCLEAR CORPORATION
I NTERAIATI ONAL
INTERNATIONAL
INTERNATIONAL
INTERNATIONAL
INTERNATIONAL
NUCLEAR
NUCLEAR
NUCLEAR
NUCLEAR
NUCLEAR
NUCLEAR DATA COMMITTEE
NUCLEAR DATA COMMITTEE
NUCLEAR DATA COMMITTEE
NUCLEAR DATA COMMITTEE
DATA
DATA
CATA
DATA
DATA
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
FEDERAL REPUBLIC OF GERMANY
DAVEY. We
LOS ALAMCS SCIENTIFIC LABORATORY
Po Oo BOX 1663
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
ATOMIC ENERGY ESTABLISHMENT
WINFRITH, DORCHESTER. DORSET
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
Po Oo BOX 1663
LOS ALAMCS. NEW MEXICO 87544
Uo So Ao
HANCOX, R E
ATOMIC ENERGY RESEARCH ESTABLISHMENT
HARWELL. DIDCCT
BERKS OX11 ORA
UNITED KINGDOM
EHRLICH. Ro
MANAGER, ADVANCED DEVELOPMENT
ACTIVITY
KNOLLS ATOMIC POWER LABORATORY
Po Oo BOX 1072
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
LOS ALAMCS SCIENTIFIC LABORATORY
Po Oo BOX 1663
LOS ALAMCS. NEW MEXICO 87544
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
FEDERAL REPUBLIC OF GERMANY
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
D-75 KARLSRUHE
FEDERAL REPUBLIC OF GERMANY
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
OAK RIDGE NATIONAL LABORATORY
Po Oo BOX X
OAK RIDGE. TENNESSEE 37830
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
FEDERAL REPUBLIC OF GERMANY
KANDA, Yo
KYUSHYU UNIVERSITY
FUKUOKA-SHI 612
JAPAN
KATSURAGI. So
DIVISION OF REACTOR ENGINEERING
JAPAN ATCMIC RESEARCH INSTITUTE
TOKAI-MURA, NAGA-GUN
IBARAKI-KEN 319-11
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
INSTITUT FUER NEUTRONENPHYSIK
UND REAKTOFTECHNIK
KERNFORSCHUNGSZENTRUM KARLSRUHE
POSTFACH 364C
D-75 KARLSRUHE
FEDERAL REPUBLIC OF GERMANY
KUESTERS. Ho
INSTITUT FUER ANGEWANDTE REACTORTECHNIK
KERNFORSCHUNGSZENTRUM KARLSRUHE
POSTFACH 364 C
D-75 KARLSRUHE
FEDERAL REPUBLIC OF GERMANY
LEE. Jo Do
LAWRENCE LIVERMORE LABORATORY
PO OO BOX ece
LIVERMORE, CALIFORNIA 94550
Uo So Ao
MA IENSCHE IN, FoCo
DIRECTOR. NEUTRON PHYSICS DIVISION
OAK RIDGE NATIONAL LABORATORY
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
KERNFORSCHUNGSZENTRUM KARLSRUHE
POSTFACH 364C
D— 75 KARLSRUHE
FEDERAL REPUBLIC OF GERMANY
MC NALLY, JoRo
OAK RIDGE NATIONAL LABORATORY
Pe Oo BOX X
OAK RIDGE. TENNESSEE 37830
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
Po Oo BOX 2351
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 ALAMCS SCIENTIFIC LABORATORY
Po Oo BOX 1663
LOS ALAMOS, NEW MEXICO 87544
Uo So Ao
PEREY. FoGe
OAK RIDGE NATIONAL LABORATORY
Po Oo BOX X
OAK RIDGE, TENNESSEE 37830
Uo So Ao
NAITO. Yo
JAPAN ATOMIC RESEARCH INSTITUTE
TOKAI-MURA, NAGA-GUN
IBARAKI-KEN 315-11
JAPAN
PERRY. AoMo
OAK RIDGE NATIONAL LABORATORY
PoOo BOX X
OAK RIDGE, TENNESSEE 37830
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
ATOMIC ENERGY RESEARCH ESTABLISHMENT
HARWELL. DICCOT
BERKS 0X11 OKA
UNITED KINGDOM
SASAMOTO, No
JAPAN ATOMIC RESEARCH INSTITUTE
TOKAI-MURA, NAGA-GUN
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
JAPAN ATOMIC RESEARCH INSTITUTE
TOKAI-MURA, NAGA-GUN
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
FEDERAL REPUBLIC OF GERMANY
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
ATOMIC ENERGY RESEARCH ESTABLISHMENT
WINFRITH, DORCHESTER. DORSET
UNITED KINGDOM
STEEN. Ne
BETTIS ATOMIC POWER LABORATORY
Po Oo BOX 79
WEST MIFFLIN. PA 0 15122
Uo So Ao
STEWART, Lo
LOS ALAMOS SCIENTIFIC LABORATORY
Po Oo BOX 1663
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
ATOMIC ENERGY ESTABLISHMENT
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
LOS ALAMCS SCIENTIFIC LABORATORY
Po Oo BOX 1663
LOS ALAMCS. NEW MEXICO 87544
Uo So Ao
WE INSTOCK, Eo Ve
BROOKHAVEN NATIONAL LABORATORY
UPTON, NEW YCRK 11973
Uo So Ao
WALLER. Fe
INSTITUT FUER NEUTRONENPHYSIK
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
ATOMIC ENERGY ESTABLISHMENT
HARWELL. DIDCOT
BERKS 0X11 ORA
UNITED KINGDCM
YOUNG. PeGo
LOS ALAMCS SCIENTIFIC LABORATORY
Po Oo BOX 1663
LOS ALAMCS. NEW MEXICO 87544
Uo So Ao
YUMOTO. Re
PLUTONIUM FUEL DIVISION, TOKAI WORKS,
POWER REACTOR AND NUCLEAR FUEL
DEVELOPMENT CORPORATICN
MURAMATSt. TOKAI-MURA.
IBARAKI-KEN 219-11
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
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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