International Atomic Energy Agency

I N

DC

INTERNATIONAL

NUCLEAR

INDC(NDS)-262
Distr. G, NC

DATA

COMMITTEE

11th IAEA Consultants' Meeting of the
NUCLEAR REACTION DATA CENTERS

Obninsk, 7-11 October 1991

SUMMARY REPORT

Edited by
H.D. Lemmel
March 1992

IAEA NUCLEAR DATA SECTION. WAGRAMERSTRASSE 5. A-1400 VIENNABSDC(NDS)-262
Distr. G, NC

11th IAEA Consultants' Meeting of the
NUCLEAR REACTION DATA CENTERS

Obninsk, 7-11 October 1991

Abstract: This report summarizes the 1991 co-ordination meeting in Obninsk, Russia, of
the national and regional nuclear reaction data centers, convened by the IAEA at regularintervals. The main topics are- the international exchange of nuclear reaction data by means of the "EXFOR" system,and the further development of this system,- the "CINDA" system as an international index and bibliography to neutron reaction
data,- the sharing of the workload for speedy and reliable nuclear data compilation,- the exchange and documentation of evaluted data libraries in ENDF format,
with the goal of rendering data center services to data users in IAEA Member States bymeans of computer retrievals, online services and printed materials.

from left to right
Aleksander Korotaev, FEI, foreign relations
Marina Ulaeva, CJD, programming engineer
K.I. Zolotarev, CJD
Liang Qichang, CNDC
Olga A. Pakhomova, CJD
Larisa Botjanovskaja, CJD, technical secretary
Claes Nordborg, NEA-DB
S.M. Nasyrova, CJD
V.E. Makarenko, CAJaD (behind Nasyrova)
S.A. Maev, CJD
V.V. Varlamov, CDFECai Dunjiu, CNDC
Vladimir G. Pronjaev, CJD
Vicky McLane, NNDC
Joe J. Schmidt, NDS
V.N. Manokhin, CJD
S.Ju. Babykina, CAJaD
M. Chiba, SG
Y. Tendow, RIKEN
Hans D. Lemmel, NDS
Sol Pearlstein, NNDC
Anatoli I. Blokhin, CJD
V.A. Vukolov, CAJaD

Contents

1

Summary3

The network of nuclear reaction data centers and the
manpower situation at the centers

Annexes1

List of Participants

23

AgendaConclusions and Actions

4

Progress reports of the centers
See a detailed index on page 23

5

Seminar on Intermediate Energy Nuclear Data

6

Minutes of the INDC Subcommittee on Data Center Support

7

Disturbing mistakes in Exfor TRANS tapes, andPending Exfor retransmissions

8

Glossary of abbreviations

-1-

Summary
The eleventh IAEA Consultants' Meeting of the Nuclear Reaction Data Centers (NRDC
Meeting) took place in Obninsk in the week 7-11 October 1991. It was hosted by the Centrpo Jadernym Dannym (Nuclear Data Center) at the FEI. Dr. V. Manokhin and his staff
must be congratulated for an excellent organization of the meeting and splendid hospitality.
The meeting included the 22nd "Four-Centers Meeting" of the Neutron Data Centres andthe 12th Meeting on Charged Particle Nuclear Data Compilation.
The meeting was attended by 19 participants from 4 Russian data centers, and 9
participants from 6 foreign centers. For the list of participants see Annex 1.
The agenda is given in Annex 2.
The Conclusions and Actions resulting from the meeting are given in Annex 3.
Progress reports of the centers are given in Annex 4.
Dr. V. Manokhin opened the meeting and welcomed the participants. He emphasized theimportant functions of the network of the Nuclear Reaction Data Centres to satisfy theworldwide nuclear data needs through the center-to-center data exchange in the internationallyagreed formats, and in particular to stimulate nuclear data measurements, data compilationand data evaluation in those fields of nuclear sciences where new data requirements areencountered. These are primarily new data requirements-in thermonuclear fusionin new fission reactor types, specifically for burning of plutonium
in medical applicationsin space technology
in the field of intermediate energy nuclear dataand others.
Dr. J.J. Schmidt thanked the hosts on behalf of the participants. He welcomed therepresentatives of the data centers and, in particular, the strong delegations from four Russian
centers.
J.J. Schmidt was elected as chairman for the General Session of the agenda and
H.D. Lemmel for the Technical Sessions.
The Agenda was approved as given in Annex 2. Work on the agenda was scheduled for
Monday, Tuesday and Friday. Visits to the Russian data centers took place on Wednesday
morning (CJD), Thursday morning (CDFE) and Thursday afternoon (CAJaD). On
Wednesday afternoon a seminar on the measurements, evaluation and application ofintermediate energy nuclear data was held, see Annex 5.

-2-

The main problem with which the centers are presently confronted is the lack of adequate
funding and staffing. A summary of the relevant discussions is given in the following pages.
This problem has led to the creation of an INDC Subcommittee on Data Center Support ofwhich the Minutes of the 1990 Meeting are reproduced in Annex 6.
Some working papers on the EXFOR data exchange are given in Annex 7.
Finally, Annex 8 contains a Glossary of Abbreviations.
For all the other items of the agenda see the "Conclusions and Actions" given in
Annex 3.
At the end of the meeting the participants honored several most meritful center heads who
were about to retire or had recently retired:-

B.S. Ishkhanov, CDFEJ J . Schmidt, NDS
Cai Dunjiu, CNDC
A. Hashizume, RIKEN
Y. Popov, former head of CJD
S. Pearlstein, NNDC

The retirement of the latter two became known only soon after the meeting. The
participants wish to thank all of them most cordially for all they had done for the networkof the Nuclear Reaction Data Centers. The loss of so many experienced experts will bedifficult to compensate at the centers.

-3-

The Network of Nuclear Reaction Data Centers andManpower Situation at the Centers

The network of Nuclear Data Centers
National and regional nuclear reaction data centers, co-ordinated by the International
Atomic Energy Agency, co-operate in the compilation, exchange and dissemination of
nuclear reaction data, in order to meet the requirements of nuclear data users in all countries.
A brief summary of the data centers network is given below.
The nuclear reaction data centers:
NNDC
NEA-DB
NDS
CJD

-

CAJaD

-

CDFE

-

RIKEN

-

SGIP
CNDC
JAERI

-

US National Nuclear Data Center, Brookhaven, USA
OECD/NEA Nuclear Data Bank, Saclay, France
IAEA Nuclear Data Section
USSR Centr po Jadernym Dannym ( = Nuclear Data Centre),
Obninsk, Russia
USSR Centr po Dannym o Stroenii Atomnogo Jadra i Jadernykh Reakcikh( = Nuclear Structure and Nuclear Reaction Data Centre), Moscow, Russia
Centr Dannykh Fotojad. Eksp. (= Centre for Experimental
Photonuclear Data), Moscow, Russia
Nuclear Data Group, RIKEN Institute of Physical and Chemical Research,
Wako-Shi, Japan
Study Group for Information Processing, Sapporo, Japan
Chinese Nuclear Data Centre, Beijing, P.R. of China
Nuclear Data Center of the Japan Atomic Energy Research Institute,
Tokai-Mura, Japan

1. Neutron Nuclear Datal.aBibliography and Data Index CINDA:
Input prepared by NNDC, NEA-DB, NDS, CJD, CNDC
Handbooks published by IAEA
Online services by NNDC, NEA-DB (and NDS from 1992)

l.b

Experimental data exchanged in EXFOR format:
Input prepared by NNDC, NEA-DB, NDS, CJD
Online services by NNDC, NEA-DB (and NDS from 1992)

1 .c

Data Handbooks based on EXFOR published by NNDC

-4-

1 .d

Evaluated data exchanged in ENDF format:
NNDC, NEA-DB, NDS, CJD, CNDC, JAERI and others. Main data libraries:
BROND-2 (USSR)CENDL-2 (China)
ENDF/B-6 (USA)IRDF-90 (IAEA)
JEF-2 (NEA)
JENDL-3 (Japan)
Online services for BROND, ENDF/B-6, JEF, JENDL-3 by NNDC, NEA-DB (andNDS from 1992)l.e

Computer retrieval services upon request of customers:
NNDC, NEA-DB, NDS, CJD

1. f

WRENDA: compilation of requested data that are known with insufficient accuracy.
Compiled by NNDC, NEA-DB, NDS, CJD, published by IAEA

2. Charged Particle Nuclear Data (including heavy-ion reaction data)
2.aBibliography published by NNDC *)2.b

Numerical data exchanged in EXFOR format:
Input prepared by CAJaD, RIKEN, CNDC, NDS, NNDC, SGIP

2.c

Data Handbooks based on EXFOR published by NDS, CAJaD

2.d

Computer retrieval services upon request of customers:
NNDC, NEA-DB, NDS, CAJaD

3. Photonuclear Data
3.a

Numerical data exchanged in EXFOR format:
Input prepared by CDFE, occasional contributions from NNDC, NDS

3.b

Bibiliographv published by CDFE

3.c

Computer retrieval services upon request of customers:
NNDC, NEA-DB, NDS, CAJaD*) Discontinued in 1990; partly incorporated in the bibliographic system "NSR" for nuclear
structure and decay data.

-5-

Manpower Situation at the Centers
During the recent years- the manpower situation at some of the centers has deteriorated such that thecompleteness of neutron reaction data in the CINDA and EXFOR databases is nolonger granted;- at other centers the manpower situation continued to be insufficient to reach theimportant aim to create a reliable charged particle reaction database for monitor
reactions and for radioisotope production.
An essential part of the meeting was therefore devoted to the discussion of the inadequate
financial support of the nuclear data centers.

Concl.

Data Needs
The continuing needs for improvements in nuclear data accuracy were summarized
as expressed at the last INDC-Meeting in 1990 and at the Julich Nuclear Data
Conference 1991. These needs exist primarily in the following fields:-

actinide burning ("minor" actinide data)advanced reactor design (e.g. epithermal tight lattice reactors)
fusionenvironmental protection
reactor decommissioning (activation and decay data)
basic reference data such as half-lives and branching ratios

It was pointed out that these defined data needs can only partly be met by data
evaluation. In many cases new measurements will be required for which only few
facilities are still available.
In addition to contributing to satisfy above new data needs, it is the continuing
important task of the data centers- to compile currently all experimental data;- to make sure that the authors supply adequate information on the uncertainty
analysis;- to examine whether new data satisfy a WRENDA request; and- to verify whether new experimental data agree or disagree with the establishedevaluated data files.
It is most essential to keep the existing data files complete, correct and uptodate.
Once the completeness of a data file has deteriorated, it requires additional
manpower to bring the file uptodate again.

-6Concl.

Data Center Network
The data centers are convinced that their present scheme of cooperation andworksharing by well-defined criteria is successful and efficient. An optimum
between exaggerated centralization and exaggerated decentralization (both haveobvious disadvantages) has been reached.
Arguments that reductions in data production justify further reductions in data
center staff must be rejected, because staff has been reduced already more than canbe justified by this argument.
Inefficiencies are known to exist for the following reasons which are out of thecontrol of the centers- Different computer configuration at the centers permitted only a limited exchangeof data file management software. This situation will improve by the changeoverof NDS to a VAX computer. But not all of the centers have the possibilities oftransferring their operations to a VAX computer.
- Staff discontinuities (primarily at the international centers NEA-DB and NDS)
absorb additional manpower for training and are responsible for occasional poor
quality compilation, which, in turn, absorb additional manpower at all centers
for the correction of compilation mistakes.
- If a single post devoted to charged-particle data compilation would be added to
one of the existing Centers, this could be more effective than a separate chargedparticle data group elsewhere with a staff of 3.
- Additional competent groups experienced in measurement, compilation andevaluation of various types of charged-particle nuclear data would be mostwelcome to join the network.

Available Manpower
Concl.

The staff situation at the centers is now such that the data needs and the
expectations of data center customers cannot be fulfilled to a satisfactory degree.
In particular, the EXFOR and CINDA files are no longer complete and show
disturbing gaps for recent data. Staff reductions at the centers were such that noneof the centers is still in the position to compile new data fast and to perform thenecessary completeness checks. The value of the data files is seriously affected bythis lack of completeness. The INDC is most alarmed about this development andhas formed a Subcommittee on Data Center Support. The Minutes of thisSubcommittee taken from the INDC Meeting Minutes are attached as Annex 6.
Since the time of the INDC Meeting, the situation has become even worse due tostaff reduction at NNDC and due to staff discontinuity and temporary post
vacancies at NEA-DB and NDS.
NDS actions to approach national authorities for additional support of data center
activities, had no success so far.

-7-Statement from NNDC on the effectiveness of the regional
responsibility model for exchange of neutron data
Prior to 1965, the NNDC compiled experimental neutron data worldwide. Since then asharing of the load with other centers has reduced the NNDC regional responsibility to the
U.S. and Canada with no loss of information because of the data exchange among theregional centers. This has resulted in great cost savings to the U.S. especially during theinformation explosion due to new and powerful accelerator sources, efficient detectors andincreased computerization.
The use of NNDC permanent staff has been an important aid to the compilation of U.S.
and Canadian data. For over 25 years, these measurers have developed confidence in the
NNDC handling of their data because they have been dealing with the same physicist (V.
McLane) who helped set up the storage and retrieval system and fully understands thesubtleties in the physics of data that can arise. It is believed that U.S. measurers willstrongly insist the NNDC itself continue to provide this same service and will protest thedelegation of this service to any other person or center.
The continuation of regional responsibility is the best interest of U.S. and Canadianscientists.

The NEA Data Bank's role in the NRDC network

The NEA Data Bank has, within the NRDC network, been involved in the compilationof neutron data and references into the EXFOR and CINDA systems covering Japan and theWestern European countries. The division, within the network, of the work in geographicalareas has been felt to be very efficient due to, among others, the following reasons:(1)

Closeness to the scientists producing and using the data compiled.

(2)

Diminishing of language problems within each area (translation and understandingof articles and laboratory reports published in the area concerned).

(3)

Keeping the network and the working tools (dictionaries etc.) alive by active
discussions and exchange of information between centers working on the same
subjects.

At present, the exchange of nuclear data is considered to be of highest prio'rity in the
1992 programme of work of the NEA Data Bank. The Data Bank's future involvement in
the NRDC network will be reviewed by the newly established NEA Science Committee.
This review will be one of the first tasks of this Committee.

-9List of Participants

CJD Obninsk, Russia

V.N. Manokhin
A.V. Ignatjuk
V.G. Pronjaev
A.I. Blokhin
S.A. Maev
O.A. Pakhomova
S.M. Nasyrova
K.I. Zolotarev
V.V. Vozjakov

CAJaD Moscow, Russia

F.E. Chukreev
S.Yu. Babykina
V.A. Vukolov
V.E. Makarenko

CDFE Moscow, Russia

V.V. Varlamov
B.S. Ishkhanov
V.V. Sapunenko
N.G. Efimkin

RI Sankt Petersburg, Russia

A.A. Rimskij-Korsakov
A.V. Daniel

NNDC Brookhaven, USA

S. Pearlstein
V. McLane

NEA Data Bank, Saclay, France

C. Nordborg

CNDC Beijing, China

Cai Dunjiu
Liang Qichang

RIKEN Nuclear Data Group,
Saitama, Japan

Y. Tendow

Study Group, Japan

M. Chiba

IAEA Nuclear Data Section

J.J. Schmidt
H.D. Lemmel (Sci. Sec.)

Annex 1

- 11 -11th IAEA Consultants' Meeting of
THE NUCLEAR REACTION DATA CENTRES
7 to 11 October 1991
hosted by theCentr po Jadernym Dannym
FEI, Obninsk

AGENDA
1.

General Session
1.1
1.2
1.3
1.4

Opening, election of chairman
Adoption of agenda
Status reports by participants
Conclusions and actions from last NRDC meeting:
CP-D/210p. 1+2
1.5 The Julich Nuclear Data Conference: conclusions relevantto the Data Centers
1.6 Other past meetings: conclusions relevant to the Data Centers
1.7 The network of the Nuclear Reaction Data Centers: communication,commitments, scope, manpower, priorities
1.8 Nuclear data evaluation: co-operation, documentation, discrepancies- neutron data
- CPND (compare conclusions from last meetings: CP-D/200 p. 8,
CP-D/210p. 10+11)- photonuclear data
1.9 Medium-energy nuclear data (INDC(NDS)-245)
1.10 WRENDA 92 (letter by J J . Schmidt)
1.11 Future meetings on nuclear data
- (see NDS meeting calendar)- other centers1.12 Computer matters- CJD computer- transition of NDS to VAX- other centers- networks
1.13 Customer services
1.14 Dates of the 1992 Technical NRDC Meetingand the 12th full NRDC Meeting in 1993 in Paris
1.15 Miscellaneous, conclusions

Annex 2

- 12-

2.

Technical Session: EXFOR, general
2.1
2.2

Review of actions from previous meeting (CP-D/200 p. 4-6, CP-D/210 p. 5-7)
The EXFOR System: rules, manual, dictionaries, proposals, etc.
- EXFOR porposals for photonuclear data
CP-D/211 (App. CP-M/13)
CP-C/198 with reply CP-D/215
CP-C/200 with reply CP-D/219- particle designaor in Diet. 36: CP-C/201- restructuring of EXFOR Dictionaries: CP-D/220, CP-C/203
2.3 Fission-product yield data
- review of conclusions and actions: CP-D/200 p. 10+11, CP-D/210 p. 8 + 9- status of EXFOR compilation; NDS meeting 2-4 Oct. 1991
2.4 Experiences with EXFOR TRANS tapes- pending retransmissions (paper by O. Schwerer, see Annex 7)- disturbing mistakes (paper by O. Schwerer, see Annex 7)
2.5 Miscellaneous, conclusions
3.

Technical Session: CPND and Photonuclear Data
3.1
3.2
3.3
3.4
3.5
3.6

4.

Review of CPND conclusions and actions from previous meeting:
CP-D/200 p. 8, CP-D/210 p. 10
Compilation and exchange of CPND
- comments on TRANS E009 and R006
Evaluated CPND, ENDF format (compare action 146 in CP-D/210 p. 13)
Photonuclear data
- review of conclusions and actions: CP-D/200 p. 7, CP-D/210 p. 12
Publications
Miscellaneous, conclusions

Technical Session: Neutron Nuclear Data
4.1

4.2
4.3
4.4
4.5
4.6

4.7
4.8
4.9

CINDA
- review of conclusions and actions: CP-D/200 p. 2 + 3 , CP-D/210 p. 3 + 4- compilation, completeness, etc.
EXFOR completeness
Important neutron data not covered in EXFORWRENDA, technical matters
Evaluated data files
ENDF- review of conclusions and actions: CP-D/210 p. 13- computer codes- NLIB codes
Fission product yield data
Nuclear model parameters (NDS meeting)
Miscellaneous, conclusions

- 13-

Annex 3

IAEA Consultants' Meeting ofRepresentatives of the Nuclear Reaction Data Centres
Obninsk, 7-11 October 1991

CONCLUSIONS and ACTIONS
Data Center Network
Concl.

A paper describing the Data Center Network in more general terms andwithout details would be helpful.

Act. NDS

to prepare a paper describing the Data Center Network, and to circulate it tothe other centers for review.

Act. All

to circulate papers on and by Nuclear Data Committees in their countries(block diagrams).

Data Center Co-operation
Concl.

NEA-DB will invite to data evaluation working group meetings observers from
NDS and (max. 2) from non-OECD countries. The next working group on FP
data will be in Mito, 28-29 May 1992.

Act.
NEA-DB

to inform NDS timely about such meetings.

Act. NDS

to try to obtain funding for the attendance of such observers and to carefully
select suitable experts.

Concl.

the 5-months visit of Dr. Varlamov (CDFE) at NNDC has laid the ground fora fruitful co-operation between CDFE and NNDC+LLNL in the field ofphotonuclear data. The resulting EXFOR TRANS tapes, which were brought
to the meeting, were highly appreciated.

Act. NDS

to write a letter of the Agency's encouragement for the work of CDFE and toinvestigate possibilities of further support, e.g. by a research contract.

Act. NDS

to investigate possibilities of support for a CAJaD-RIKEN co-operation in thefield of charged-particle nuclear data for monitor reaction and radinuclide
production.

- 14Concl.

NDS staff (O. Schwerer and R. Arcilla) had visited NEA-DB and NNDC for
preparing the transfer of software to the new NDS VAX computer. NDS
gratefully acknowledges the assistance of the two centers in this matter. In
addition to the successful worksharing in data compilation, the centers will now
organize a worksharing in software development for data file management on
a VAX computer.

Act. NDS

to communicate fast to NEA-DB and NNDC the final choice for softwaretransfer and to prepare the visits of NEA-DB and NNDC staff at NDS after the
installation of the VAX computer (i.e. the visits will not be before 1 Jan.
1992).

Concl.

To intensify the software exchange among the centers it would be mostbeneficial if CJD, CAJaD and CNDC could find means to upgrade their VAX
computer facilities. Also CDFE needs improved computer facilities (PC andVAX) for efficient participation in the data centers network.

Concl.

The change of NDS to a VAX computer will cause difficulties for the two
Japanese CPND centers who will continue to work on IBM compatible (VAX
incompatible) Japanese computers. These difficulties will have to be studied
and solved.

Concl.

Difficulties in e-mail connections seem to come, at least partly, from Bitnet,
whereas Internet seems to function well. DB will link to Internet in Nov.
1991. NDS is likely to get an Internet connection after the VAX computer has
been installed.

Concl.

CJD will continue to compile data from, and to render data center services toall countries of the previous USSR, except for the case that one of thesecountries explicitly requests to change over to NDS.

Concl.

Data center services for the former GDR are being shifted from NDS to
NEA-DB.
WRENDA

Concl.

The preparations for WRENDA 92 proceed as outlined in the circular letters
by J.J. Schmidt of 24 July 1991 and 6 August 1991. It was emphasized thatrequests should be reviewed carefully and that old requests (before 1980)
should be removed unless they are replaced by a new request.

Act.
NEA-DBIt was confirmed that NEA-DB will send their entries in computerized form.

- 15-

Annex 3
(cont.)

Act. CJD(Nikolaev)

Dr. Manokhin announced that CJD is not only reviewing USSR requests butthat they have also comments on requests originating from other countries.
Dr. Nikolaev was asked to send these comments before the end of November
1991, so that NDS can still submit them to the national reviewers.

Act. NDS
NNDC

to define how NDS could temporarily assist NNDC in the US CINDA
coverage.

CINDA
Act. CJD

to continue to cover for CINDA and EXFOR the baltic countries for the time
being, unless these countries request a change.

Concl.

The CINDA work of CJD, which was reorganized in the past years, wasappreciated as functioning smoothly. CJD can now receive small files of
CINDA entries (up to 100 records) by electronic mail, larger files should besent on floppy diskettes.

Reco

The use of floppy diskettes for the transmission of CINDA entries is
encouraged. Note that CJD can use only 1.2 MB 5lA inch diskettes, not 1.4
MB 3V4 inch diskettes.

Act. CNDC CNDC is asked to cover Chinese literature for CINDA and to send the entries
to NDS.

EXFOR
Act. NDS

to update the EXFOR Manual, because this will not be possible to be done at
NNDC.

Act. NDS

to verify regularly that the other centers receive all TRANS tapes.

Act. NNDC to verify whether the conversion of the temporary EXFOR files 6, 7, 8 has
been finished; if not, remind the centers what must still be done.
Act. All

to develop procedures for automatic renormalization of EXFOR data, inparticular to use renormalized EXFOR data for graphical comparisons between
evaluated and experimental data.

- 16-

Concl.
Act. AH

Attention is drawn to the list of disturbing mistakes in EXFOR TRANS tapes(see Annex 7).
Additional items that should be remembered are:- it is essential that in case of several bibliographic references in an EXFOR
entry, the primary reference is given first: it is this reference which is usedby computer codes (plotting) to identify the data set;
- corrections done to an EXFOR entry must be described briefly under
HISTORY; to know what has been changed is most essential to receiving
data centers and customers.

Urgentactionon Allto make sure that the entries contained in the list of "Pending Exfor
retransmission" (see Annex 7) are corrected and retransmitted as pointed out
in the relevant CP-memos. Centers should realize, that these entries could not
be added to the EXFOR master libraries of the other centers. Compilations are
made for the waste paper basket if such requests for corrections andretransmissions are not followed promptly.

Action
McLaneto remind the other centers of retransmissions that she had requested earlier
during her work for the barn-book.

Act. NDS

to monitor regularly that requests for retransmissions are fulfilled.

Act. NDS

Following Action 61 of CP-D/210 of the 1990 NRDC Meeting, F. Chukreev
submitted a sample EXFOR entry of gamma data from "short-living isomers",
using "-S" as an isomer extension. NDS will review this formalism andsubmit comments in a CP-Memo.

Concl.

Memo CP-C/201 about shortening Diet. 36 with respect to Particle Designators
is adopted, but implemented only after centers have updated their codes(particularly the Exfor Check programs) accordingly.

Concl.

Memo CP-C/203 about the NNDC Dictionary System was studied and founduseful. Additional work will be needed to include all the information requiredby the NNDC System in the overall Dictionary System.
This should be done jointly by NNDC and NDS when NDS changes over tothe VAX computer. NNDC is requested to transmit their dictionary file to theother centers for information. A new Dictionary transmission format will haveto be designed by NDS.

Act. NDS
NNDC

Concl.
Act. NDS

Memo CP-D/220 about structuring of information in certain dictionaries is
adopted with the modification that dashes should be omitted from the first field(col. 1-11).

- 17-

Annex 3
(cont.)

Reco toCJD andCAJaDCJD and CAJaD are asked to update their EXFOR programs such that retransmissions can be done at subentry level (instead of retransmitting entire
entries). V. McLane gave to Olga Pakhomova Fortran codes for this purpose
which could be forwarded also to CAJaD.

ManualupdateneededAct. AllIn the EXFOR record identification field blanks are accepted instead of leading
zeros. In cols 72 to 78 zero and blank is equivalent. Where necessary, centersshould update programs accordingly.

Concl.

F. Chukreev has produced a PC code for the checking of EXFOR entries
supplementing the ANDEX code for EXFOR compilation by V. Osorio. So
far the code is in Russian only.

Fission-product Yield Data
V. McLane gave a summary of the IAEA CRP-meeting 2-4 Oct. 1991. Within the workof this CRP the Rider data are machine converted to raw Exfor data (not checked), and thesedata are checked and corrected by specialized physicists and converted to final Exfor entries.
Specialized physicists for this work areAct.

Rider for area 1
M. James for area 2
Wang Dao and M. Lammer for area 3
Goverdovskij for area 4
They should also receive author proofs of these Exfor entries.

Concl.

The FY entries in EXFOR must be complete. If certain data are found to be
wrong or deficient, such information should be entered under the keyword
CRITIQUE, but the entry must be kept in the file.

Concl.

A new Status code "NCHCKD" is introduced in EXFOR for labelling theuncheched raw Exfor data.

Act.
Lammerto send the area 4 FY entries to CJD on tape: so far they have them on a listing
only.

Act.
NEA-DB
NDS
CJD

1. to transmit immediately the new unchecked FY data with the Status code
NCHCKD added;
2. thereafter to continue to review and correct these entries.

- 18Reco

FY compilers should ask the experimenters for precursor data and include suchinformation under DECAY-DATA.

Act.
Lammer

The requests resulting from the FY-CRP-Meeting should be included in
WRENDA. M. Lammer should take care that these are routed through theproper channels.

Act. NNDC The FY-CRP-Meeting requested that EXFOR retrievals by FP nuclides be
NDSpossible. While the NDS EXFOR index provides this possibility, it is not yet
possible in the VAX EXFOR retrieval system, which should be updated
accordingly.
Act.
Nordborg

Act.
Blokhinto advertise and demonstrate the EXFOR system at the Tokai FP data meeting;it was found out that many FP physicists have insufficient knowledge about
EXFOR (format, contents, how to make use of it).
Dr. Blokhin received from Dr. Greshin (Moscow Engineering and Physics
Institute) an evaluated data file with FPY data. This was converted at CJD to
ENDF format. Dr. Blokhin is asked to transmist this file as soon as it has
been checked and approved.

Evaluated Neutron Data
Concl.

JEF-2 was so far distributed only to labs who did benchmark testing. The final
JEF-2 will be released after benchmark testing. This is highly appreciated by
the other centers.

Act.
NEA-DB

to distribute JEF-2 to the other neutron data centers.

RecoDB

NEA-DB is encouraged to produce a new report (similar to the report JEF-1)
comparing characteristics values (thermal cross-sections, resonance integrals,etc) of the main ENDF formatted libraries.

Act.
NNDC

As far as not yet done send the ENDF/B-6 point data library to the otherneutron data centers.

Act. NDS

The release of CENDL-2 was highly appreciated. NDS is presently checking
the file and will forward it to the other centers as soon as possible.

Act. CJDOf BROND-2 NDS had received a preliminary file, mainly for considerationin the FENDL project. CJD is asked to transmit the final BROND-2 as soon
as possible.

- 19-

Annex 3
(cont.)

Concl.

CENDL-2 and BROND-2 include files partly in ENDF-5, partly in ENDF-6
format. This is not disturbing; the ENDF processing codes can handle both.

Act. All

When preparing evaluated data libraries, characteristic values (thermal crosssections, resonance integrals, etc) should be quoted in the text or inaccompanying documents together with their uncertainties: however, thesevalues (and uncertainties) would be better usable if they were in a computerreadable file.

Concl.

The now established evaluated data files will continue to exist and to be
updated for the time being. Even the OECD working groups have decided tocontinue ENDF/B, JEF and JENDL as separate libraries, for a variety ofreasons. However, uncoordinated parallel efforts must be avoided.

Concl.

A. Ignatjuk and S. Pearlstein stressed the need for close co-operation forimproving the existing evaluated data libraries. In general, all libraries
appear to be rather good for existing
reactors but show disturbing
discrepancies in data-types needed for advanced reactors and some other new
applications. Some examples that were mentioned, follow.
- U-238 capture: good agreement between BROND-2 and ENDF/B-6.
- U-235: fairly good agreement between ENDF/B-6, BROND-2 andJENDL-3, but also some unnecessary disagreements which could be solved
by a joint effort.
- Np-237: now sufficiently good agreement for fission; the previous big
discrepancies in n,2n have nearly been solved.
- Cm-242: in the few-MeV region which is important for incineration there
are drastic discrepancies in the order of 50%; for n,2n the discrepancies
exceed a factor of 10!
- dosimetry reactions: good agreement in general, but still large differencesin the cross-section wings which are important for certain applications.

Act. All
Evaluators

to intensify bilateral contacts for coordination of data evaluation.

Act. NDS
NEA-DB
NNDC

to try to find means and funding for the participation of CJD and CNDC in the
joint efforts to improve the evaluted data files.

Act. Allto make use of the NNDEN Newsletter to coordinate evaluation efforts.

-20-

Act.
NEA-DB

to investigate whether NNDEN can be supplemented by a table showing whoplans to work on what evaluation.

Concl.

Unique international files could be achieved so far only in limited areas suchas
- standards: ENDF/B-6- dosimetry: IRDF-90- fusion: FENDL, possibly to be coordinated with EFF.

Concl.

At present there may be avoidable duplication of efforts in the detection ofdefaults in data libraries. The situation may be improved by the following
action:Act. All
to collect lists of known defaults in the evaluated data libraries, communicate
Librarythese lists to the other data centers, possibly to include such lists in theOriginators forthcoming issue of NNDEN.
Act. NDSThe ENDF utility codes version 6.6 have been distributed by NNDC. NDS
will distribute the new version of the ENDF pre-processing codes by Red
Cullen.

CPND
Reco
SapporoDr. Chiba gave a report on the Japanese NRDF system and his efforts toconvert NRDF data to EXFOR and vice versa. He distributed printed reports
on NRDF for 1989 and 1990 which are in Japanese but with sufficient portions
in English. Dr. Chiba's continuing efforts to convert NRDF data to EXFOR
are acknowledged and he is strongly encouraged to continue this work,
primarily for differential CPND.

Concl.

The CPND agreement reached at earlier meetings for the co-ordination of
CPND compilation is confirmed. F. Chukreev continues to act as coordinator. CPND compilers should communicate with Dr. Chukreev directly
and frequently, (with copy to NDS).

Act.
McLaneto distribute, after consultation with F. Chukreev, the Exfor converted
CPND file of R. White (Livermore) on light-element neutron producing
reactions.

Act. NDS

to contact CAJaD and Arzamas to obtain the quasi-Exfor file of experimental
data underlying the Arzamas evaluation.

Reco
Chukreev

to compile and evaluate the Bll + p reaction.

-21-

Annex 3
(cont.)

Reco
CAJaD
CNDC
RIKEN

to continue to work, under mutual consultation, towards compilation andevaluation of monitor reactions and of medical radioisotope production reactions
according to the needs defined at earlier meetings.

Act. NDS

to try to arrange a CRP on this topic which would be an essential stimulance
for finding support for this work at CAJaD, CNDC, RIKEN and perhaps
others.

Concl.

F. Chukreev points out that no monitor data for deuteron beams exist and that
there is a strong need for such data.

Concl.

For the time being evaluated CPND should continue to be compiled in
EXFOR, because this can easily be done without delays. Conversion of suchdata to ENDF format can be done in a second step.

Act. NNDC to produce a "Short guide to ENDF" for charged-particle data evaluators andsend it to Dr. Chukreev.
Concl.

F. Chukreev distributed the memo CP-A/61 containing formulae of conversion
factors for thick target yields. This was appreciated. It should be included in
Lexfor.

Concl.
Act.
Tendow

Dr. Tendow had recently sent to NDS the EXFOR TRANS tape R006. A few
comments by O. Schwerer were given to him and Dr. Tendow was asked to
update the entries accordingly.

Concl.

F. Chukreev plans to hold a CPND workshop on EXFOR and CPND
evaluation procedures. He also plans a new book giving the contents of the
non-neutron EXFOR database with a preface in English.

Photonuclear Data
Concl.

CDFE has established close contacts with NNDC and LLNL. A large numberof EXFOR entries was updated, compiled and transmitted on tape at the timeof the meeting. This was much appreciated by the meeting, and CDFE wasencouraged to continue this work. A "Photonuclear Data ooperation Project
between CDFE and NNDC" was formulated; see Annex 4.3.

Concl.

CDFE has insufficient computer facilities. For the time being work is
restricted to an IBM compatible PC. Additional software, mainly for using
ENSDF and NSR on a PC, will be required. Work will concentrate on
EXFOR compilation and data evaluation.

-22-

Concl.

In the course of the CDFE-NNDC co-operation, various proposals for EXFOR
coding of photonuclear data have been formulated and distributed in memos
CP-C/200 and CP-D/219. These were adopted.

Intermediate Energy Nuclear Data
A seminar on intermediate energy nuclear data was held, see Annex 5.
Reco
NNDC

NNDC intends to issue an atlas of available intermediate energy data.

Reco AllFor this purpose all centers were asked, as fas as manpower permits, toincrease their efforts to compile intermediate energy data in EXFOR, including
neutron data and CPND.

Code ComparisonsConcl.
Act.
Ignatjuk

Additional participants in the model code intercomparison exercise by NEADB can still be accepted.

Customer Services
Concl.

Request statistics must be interpreted with caution:- more institutes are now able to process large data libraries; consequently,
a single request for an entire library is now more meaningful thanpreviously many requests for special retrievals;- on the other hand the new on-line services have again a tendency to a larger
number of smaller requests;- request statistics cannot show multiple usage of a single data request.

Concl.

All centers encounter increasing user interest for PC codes and for specialized
data files for use on PC's.

Concl.

NNDC and NEA-DB encounter significantly increasing statistics for their
online services. NNDC also offers services by FAX for good quality prints
and graphs.

- 23 -

Act. All

Annex 3
(cont.)

to do more public relations work;
to advertise data center services at suitable meetings;
to exchange demonstration materials for use at meetings;
to prepare a package describing the services offered, for distribution toindividuals (e.g. students)

Meetings
The 1991 Julich Nuclear Data Conference had identified continuing nuclear data needs
for specific applications, and had given the opportunity to advertise the work of the data
centers. NEA-DB has prepared CINDA entries (first by paper-number, now being changed
to the final page-numbers of the book of proceedings). A CINDA index will not be includedin the proceedings and NDS will be asked to publish this as an INDC report. NDS also
considers an INDC report to include those USSR papers which were not accepted forinclusion in the proceedings.
The NDS meeting list for 1991/1992 was distributed (see Annex 4.10) and an outline
of NDS meetings in 1993/94 was given.
Dr. Manokhin reported that the future of the Kiev nuclear data conferences is uncertain.
Dr. Cai announced the CODATA Conference in Beijing 19-22 Oct. 1992.
Dr. Nordborg announced the Fission Product Nuclear Data Meeting (NEANDC
specialists meeting) to take place in JAERI/Tokai-Mura 25-27 May 1992.
The Brookhaven evaluation meeting will be 28 Sept. to 2 Oct. 1992.
It was discussed whether the 1992 Technical NRDC Meeting should be held in
Brookhaven adjacent to the evaluation meeting.
Note added in proof: The 1992 Technical NRDC Meeting is planned to be held at the
IAEA, 1-3 Sept. 1992.
The next full NRDC Meeting is supposed to take place in Paris in fall 1993.
Dr. Chukreev announced that the next NSDD network meeting has been scheduled totake place in Tashkent in October 1992.
Note added in proof: It turned out that the meeting could no be held in Tashkent.

- 25 -

Annex 4Progress Reports of the Centers

4.1

CJD progress report (V. Manokhin)

4.2

Report of CAJaD (F.E. Chukreev)

4.3

CDFE progress report (V.V. Varlamov)
Note: Dr. Varlamov also distributed the report Fotojadernye Dannye/Photonuclear
Data No. 13 1989.

4.4

Progress on nuclear data work in China (Cai Dunjiu)

4.5

The activities on CENDL, EXFOR, CINDA and WRENDA in China (Liang Qichang)

4.6

Data activities in the RIKEN Nuclear Data Group (Y. Tendow)

4.7

Status report of SG (M. Chiba)
Note: Dr. Chiba also distributed two documents- NRDF Annual Report 89- NRDF Annual Report 90
These are too voluminous to be reproduced here. Although they are in Japanese theygive valuable information on the contents of the NRDF database.

4.8

NEA Data Bank progress report (C. Nordborg)

4.9

NNDC Status report (S. Pearlstein)

4.10

IAEA Nuclear Data Section progress report (H.D. Lemmel)

Annex 4.1

CJD Progress report,
1. CIOT>A. During 1991 the CJD compiled into CT.'.DA 977 newrecords and modified 1386 records. Information on Iulich Conference was put into the catalog.
2. EXFOR. Three tapes with TRAITS 4081-4083 were preparedwith 27 entries (142 Subentries) and 32 corrected entries(518 Subentries).
The A1TDEX code for EXFOR compilation from HDS has been put
into operation on PC AT.
3. Evaluated Data.
3.1. BR01TD. A lot of efforts was spent in order to deve lop new version of BROUD-library (BRO17D-2). The selection ofevaluated data for the BROIJD-2 library, its analysis and handling have been completed mainly in 1990. Some additional checking and correction of files of the library was made this year.
For principal reactor materials the evaluated data developed by soviet specialists have beenincluded into the library.
In the case of materials used as neutrc.i standards the data reconaaended by the IA3A were accepted. Per remaining materials,
the files which soviet specialists considered as the most re—lible were taken from existing foreign libraries and used as abasis for thorough revision. As a result of such revision theevaluated data were changed or completed in correspondence withrecent experimental data and theoretical calculations (replacement of resonance parameter file, inclusion of "Che data for the;n,2n) and (n,3n) reactions and proper modification of spectraof neutron inelastic scattering, reexamination of proton production data in neutron reactions and so c.;). All materials werechecked by the EITDF Utility codes.
The description of 3R0I7D-2 will bo published in Yadernye
Eonstanty this year. The texts are ready but we need some time
to take corrections and format changes.
For further development of BROIID-2 it is neces.sary to
expand the data on radionuclide production cross sections andimprove a quality of the data on photon production in neutron
reactions.

The BROiTD-2 files together with additional files (as arule of foreign origin), which are not completely expertisedyet, are named as the FUHD-library.
3.2. Evaluations for FE1IDL.
In the framework of FB1TDL activity the files of natural
Cr, Sn and ffb from BROND-library were corrected and partiallyrevised for fuaion reactor applications. Other files (D, Be,
isotopes of Cr and Fe) from BROIID and EKDF libraries were analyzed and inter compared v/here it was possible. The 175-groupcross section library was generated for the most of these files.
Expertise of ECU (Petten) activation library and conver sion it into 175 group cross section library was done. The conditions of the sphere transmission benchmark tests for Pb provided by IAEA were analyzed and it was shown that the description of the experiment was not adequite to real conditions.
3.3» Dosimetry reactions.
The CJD file of dosimetry reactions is in process of formation. ]?or that the additional analysis of data of 30 reactions was performed and the data were corrected taking into account integral measurements. Covariance matricies are underpreparation for several data sets.
3.4» Others compilation and evaluation.
Seme practical applications in our institute required tocompile the decay data for radionuclides. The EIISDP library\-;as used as a base. Additional data wore attracted as well. The
final library for 2200 radionuclides v^s adapted on micro-VAX
and PC/AT.
Also haying in mind the requirement for practical calcu lations the CJD prepared a book of curves of experimental
photonuclear data and formed on this "case the evaluated photonuclear data for 27 elements.
4» Computers and codes.
Besides
computer EC 1033 the local network on the baseof micro-VAX-II and PC/AT was realized. There are-3 PC/AT-285
and 2 soviet PC(EC-184O, EC-1841) as well.
All the evaluated data libraries and necessary codes fordata processing and calculation were put into operation onAnnex 4.1(cont.)

3

micro-VAX. Programs IWOY-87 and AIJTSIT are used to develop
data for PS1IDL. Llonte-Carlo code BRAITD was adopted also toread the E1JDF-6 formated data as input data for neutron transport calculations and was used for description of 3e sphereneutron transmission measurements v/ith data from I21IDF/B-6 library.
Some progress is in adaptation on PC/AT programs forgraphic presentation of evaluated nuclear data (including
double differential cross sections) for its comparison.
How the CJD actively uses e-mail.

Annex 4.2
REPORT OF CAJaO
F.E. Chukreev
After the Technical Meeting of the Centers in 1990 our main concern was
the renovation of the Center equipments. After long hesitation, we decided
to connect the computer with VMS operation system. This connection will takesome time to finish. When this connection is done, we will transfer all our
database into the new system.
1.

Data Evaluation

During the last two years the following evaluation of charged particle
reactions were done:
C-12(p,pn)C-ll
C-12(He-3,x)C-ll
AL-27(He-3,x)Na-22
Cu-65(He-3,2n+p)Zn-65
Cu-65(He-3,2n)Ga-66

up to 1000 MeV
up to 30
MeV
up to 100 MeV
up to 70
MeV
up to 50
MeV

These data will be presented in a separate report on this meeting.
2.

Preparation of new data for EXFOR library

TRANS A024 has been transmitted in 1991 (05.04.91) and TRANS A025 is readynow. It contains some new publications and corrected old ones. The TRANS
have been written on diskettes. The transmission of data is preferably on
diskettes rather than on tape, because
a. the price of mailing diskettes is low,b. our experience has shown that the preservation of information is verygood.
I cannot judge the size of neutron data entries and TRANS, but chargedparticle nuclear data can be transmitted on floppy diskettes. I believe thatafter the connection to the new computing system we will have the possibilityof correcting old errors in transmitted entries. This is a very complex
problem for us today.
3.

Checking code for EXFOR

We are using IBM-compatible PC NEIRON (USSR product) forchecking EXFOR entries to transfer our data into the new system.

input

and

The code for checking EXFOR entries has been written.
This code is
directed to check charged-particle data. A demonstration of data processing
can be arranged during your visit to the CAJaD if you would like to see.
The quality of checking with our new code by CAJaD and other Center
entries is acceptable, but this code cannot find some errors.
For example, this code does not find errors:
invalid DATA unit PER-CENT
orEN-MAX<
EN-MINWe are constantly increasing the possibility of finding errors, but I canassure that to create a checking code for EXFOR entries which could find all
errors is impossible.

Annex4.3

CDFE PROGRESS REPORT - 1991
I.N.Boboshin, V.V.Varlamov, N.G.Efimkin, V.V.Sapunenko,
M.E.Stepanov

CDFE, Institute of Nuclear Physics,
Moscow State University, Moscow 119899, USSRThis report contains thereview of the works cariedout by CDFE since the beginnig of 1990 till the middle of1991 .
The main
fieldof
CDFE'sactivity
remains
theproductionof photonuclear experimental data files using
EXFOR format.
The new consecutive exchange magnetic tape
(CDFE TRANS M010), which contains the data from 38 articles
published in USSR and abroad has been finished.
In the beginning of 1991 during
the CDFE
head
Dr.V.Varlamov's visit to USA BNL NNDC the addition of 100
new EXFOR ENTRIES has
been done to the photonuclear data
fund.
So the total number of CDFE-raade MO-ENTRIES havereached about 430 (M0001-M0500 with several blanks).
Besides that the last version of Dr.B.Berman's EXFOR
library(L0037-L0059)
ofphotonuclear
reaction
cioss
sections obtained using quasimonoenergetic photon beams havebeen reprocessed in accordance with thenewrequirementsof EXFOR format for photonuclear data.
In addition the new magnetic tape was found in the USA
National
Institute of Standards and Technology, whichcontains a lot of photonuclear data have been diggitizedpreviously in USA National Bureau of Standards fphotonuclear
group of Dr.E.Fuller). Now these data are in preparation forincluding in CDFE photonuclear data EXFOR fund.

During Dr.V.Varlamov's visit the Draft Proposals of
Photonuclear Data Cooperation Project between MSU INP CDFE
and USA BNL NNDC (with participation of scientists ofLawrence
Livermore Laboratory) havebeen
produced. The
main aim of the Project (see Annex) is the progress incompilation
andevaluationofphotonuclear
data.
In
connection with this aim a number of new additions to EXFORDICTIONARIES and LEXFOR have been made by CDFE together
with NNDC (Memos CP-C/199,200) .
For progress in the field of photonuclear
data
evaluation
the solving of the well known problem ofsystematic discrepancies between the results of experiments
fulfilled using bremsstrahlung and quasimonoenergetic photon
beams isvery important. Sticking the photonuclear data
evaluation programm CDFE has published in 1989 the Preprint/I/, in which the possible reasons of the discrepancies inshapes and amplitudes of the photonuclear reaction crosssections
obtainedwithbremsstrahlung
gamma-rays
andquasimonoenergetic photons from annihilation in flight offast positrons have been investigated. The influence ofthe quasiminoenergetic photon spectrum parameters upon the
structure of cross sections was studied.
It
was shownthat
the differenceofthespectrum's
shape
from
the delta-function assumed in traditional scheme ofthequasimonoenergetical photons experiment makes inconsistent
the result interpretation as a reaction cross section
namelly. It was shown that this result is really only thereaction yield.
The energy resolution overestimation
follows thisdifference.
The
methodofreduction,
independent
on nuclear models, a priori information,andany regularization / 2 / was used to improve the energy
resolution. It was shown that the data analysis taking
into account the shape of the quasimonoenergetic photon
spectrum results in better agreementwith the structuresof bremsstrahlung data.

Annex 4.3(cont.)

Sticking the
programofphotonuclear
data
information publication the CDFE work on publishing of theannual Information Bulletins and Indexes"Photonuclear
Data",
containing
the systematized information about theexperimental works on photo- and electronuclear reactions
andinversereactions of radiative capture has been
continued. The bulletin N 13 "Photonuclear Data-1989" /3/
has been publishedin 1990.
The CDFE has prepared"Photonuclear
Data Index
1986-1990" / 4 / included
thecorrected and added information for 1986-1989
periodandnewinformation for 1990. The Index will be published inthis year.
In addition to EXFOR-activity CDFE has continued theactivity in thefield
of using other international
computer files such as ENSDF and NSR for processing ofrequests of soviet scientists at first from universities andinsti tutes.
Within the reviewed period CDFE have received
andprocessed about
200 requests concerning
bibliographicalinformation (EXFOR, NSR) and about 300 requests concerning
numerical
photonuclear
and charge-particle data (EXFOR,ENSDF).
There are a serious problems with computer in CDFE now.
The main CDFE computer "ES-1022" is more then 10 years oldand doesn't operate well now.
Because of hard economic
situation in CDFE,
Institute of Nu/clear
Physics,
andMoscow
State University at all there are no possibilities
for receiving of new sufficiently
powerful computer. The
new CDFE IBM PC computer does not solve all problems of CDFE
and of new CDFE-NNDC
cooperation
in
the
field
of
photonuclear
data processing and evaluation. So CDFE need
IAEA help.

REFERENCES
1.

V.V.Varlamov, N.G.Efimkini N.A.Lenskaja,A.P.Chernjaev.
The Investigation of the Reasons for Discrepancies inResults of Photonuclear Experiments at the Beams ofBremsstrahlung and Quasimonoenergetic
Gamma-Quanta.
The Problem of Interpretation.
MSU INP Preprint-89-66 /143.,S9g9.

2.

V.V.Varlamov, B.S.Ishkhanov, Ju.P.Pyt'ev, N.G.Efimkin.
The Energy Resolution Improvement by the Method of
Reductionin Photonuclear Experiments.

MSU INP Preprint-91--2.5/239 ^4991 .
3.

I.N.Boboshin, V.V.Varlamov, V.V.Sapunenko,
M.E.Stepanov,
V.V.Surgutanov.
Photonuclear Data-1989. CDFE Information Bulletin N 13.
Izdatel'stvo Moskovskogo Universiteta, 1990.

4.

V.V.Varlamov, M.E.Stepanov, V.V.Sapunenko.
Photonuclear Data Index 1986-1990.
Izdatel'stvo Moskovskogo Universiteta, 1991.

Annex 4.3

ANNEX(cont.)DRAFT PROPOSAL
Photonuclear Data Cooperation Project
between
CDFE - Moscow State University
and
NNDC - Brookhaven National Laboratory
Project subject:
Participating organizations:

Personnel:

Project duration:

Production of experimental and evaluated photonuclear data files.
USA BNL NNDC
USA LLNLUSSR MSU CDFE.
Dr. V. McLane, NNDC (USA)Dr. V. Varlamov, CDFE (USSR)
Dr. S. Warshaw, LLNL (USA).
First phase, 3 years (June, 1991 - June, 1994).

CDFE RESPONSIBILITY
1.

give NNDC all CDFE-compiled photonuclear data prepared up to June,
1991 (ENTRIES M0001 - M0500).

2.

send NNDC all compiled photonuclear data in EXFOR format which CDFE
will prepare in the future.

3.

prepare and give NNDC all photonuclear information from the CDFE Information Bulletins (NN 1-14 and subsequent) in computer-readable form
for merging them in the CINDA system.

4.

organize EXFOR compilation of the experimental data contained on thetape obtained from the USA NIST.

5.

give NNDC all new materials (Bulletins,Indexes Reviews etc.) to be published by CDFE in the future.

6.

give NNDC the description of CDFE's photonuclear data evaluation softwareand the software itself.

7.

organize the EXFOR-compilation of experimental papers and the digitizingof the data as agreed by Dr. S. Warshaw and Dr. V. Varlamov.

8.

organize the creation of the evaluated photonuclear data in ENDF format
as agreed by Dr. S. Warshaw and Dr. V. Varlamov.

9.

organize the permanent contacts with LLNL by means of e-Mail.

10.

promote visits of USA scientists to CDFE .

NNDC RESPONSIBILITY
1.

give CDFE the latest version of Berman's compilation in EXFOR format(L0001-L0059).

2.

give CDFE Fuller's photonuclear digital data obtained from USA NIST.

3.

give CDFE the various software for VAX and IBM/PC processing of the
NSR- EXFOR-, ENDF/B- and ENSDF data.

4.

merge the photonuclear data from the CDFE Information Bulletins with thedata into CINDA system if staff available.

5.

give CDFE the CINDA system software (for VAX) and the CINDA photonuclear data.

6.

study the possibilities of joint (with CDFE) publication of materials (atlases,
catalogues etc.) with photonuclear data.

7.

give CDFE various nuclear data (maps, schemes, booklets, notebooks etc.)
published by NNDC.

8.

give CDFE all photonuclear materials (published and computer) which NNDC
will receive from other (non-CDFE) sources.

9.

organize the permanent contacts with LLNL in accordance with the CDFELLNL agreement.

10.

promote visits of USSR scientists to NNDC.

Sol Pearlstein, Head N N D C

Vladimir Varlamov, Head C D F E

DateAnnex 4.3(cont.)The CDFE and LLNL Photonuclear Data Processing Activities.
REQUIREMENTS:- Photon energy range:- Photon source types:

Threshold to about 40 mev.
1. Mono2. Quasiraono
3. Bremsstrahlung

radioactive nuclei,
radiative capture
reactions (X,G),
Compton-acattering;
kinematic selections;threshold technique;(B+) -annihilation,
tagging;"whole","hardened","difference".

- Experimental categories: 1. Photoneutron production(for medicine, electronics, shielding)- quantities: Y, SIG-reactions:(G.N). (G,2N), (G,3N),.... (G.XN), (G.N+P),(G.2N+P),...
2. Specific isotope production(for a c t i v a t i o n , r a d i a t i o n damage)- q u a n t i t i e s : SIG, DA, DE, DA/DE-reactions:(G,N), (G.N+P), (G,P),(G.A)
3. Total photoabsorption(for shielding, atomic data benchmarks)- quantities: SIG
4. Photofission- quantities: Y, SIG
5. Nuclear (non-atomic) scattering- quantities: SIG

- Scope of isotopes:(with evaluation
priorities)

1. Lightest nuclei
H, He, Li, Be, B
2. Industrial and shielding materials
Al, Fe, Cu, Ni, V, Pd
3. Electronic materials
Si, Ge,4. Biological materials
C. N, 05. Nuclear fuels
Th, U, Pu, AmAnnexPROGRESS ON NUCLEAR DATA WORK IN CHINA
Cai Dunjiu
Chinese Nuclear Data Center
China Institute of Atomic Energy
P. O. Box 275 (41), Beijing 102413
P. R. China

Abstract : Recent years we have made great efforts to prepare CENDL—2
and to improve the evaluation further. Therefore, advanced evaluation andtheoretical calculation methods and programs have been or are being
developed.

1 Nuclear Data Evaluation11 ~319~211
1.1 Neutron Data for General Purpose
1.1.1 Evaluations for CENDL-2
Based on the first version of the Chinese Evaluated Nuclear Data Library(CENDL-1)[3], the CENDL-2 has been prepared. The CENDL-2 includes files
1—5 for about 50 nuclides (or elements), which were evaluated by ourselves. The
neutron incident energy range is from 10~5 eV to 20 MeV. The nuclides include
H, D, T, 3'4He, 6J Li, 9Be, m% U N, 16O, F, Na, Mg, Al, Si, P, S, Cl, 40Ar,
K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Zr, Nb, Mo, 107-109>NAg, Cd, In, Sn,
Sb, mBa,Hf,Ta,W,Au,Pb, 232Th, 235-238U, 237Np, 239'240Pu, 241Am,249Bk,249Cf.
Among them O, F (cooperated with LANL and ORNL) 241Am (withcovariance), 249Bk, 249Cf were evaluated also for ENDF / B-6, 107-1O9-NAg (including -y-production data, in cooperation with JAERI / NDC) for JENDL-3.
Most of the evaluations have been complemented with model theory calculations by using the codes (the main ones are MUP2, FUP1 etc. ) developed byourselves. Most of the evaluations have been reviewed by assigned reviewer
respectively at first. And secondly, reviewed and approved by the Working
Group of Neutron Nuclear Data Evaluation. Finally, checked through by thecodes of CHECKER, PHYCHE, FIZCON, and then accepted by CENDL-2.
Generally, most recently measured data in the smooth energy region havebeen taken into account in the evaluations. The evaluations have been compared with the newly available evaluations, and for some evaluations every effort has been made to update them significantly. The evaluated resonance4.4

parameters including those for the negaetive level(s) have been checked and adjusted if necessary via comparing the calculated cross sections with resolved
parameters with Doppler—broadened to the available point—wise data measured at thermal and resonance energy region. To ensure the "continually connection" of the group—averaged cross sections with the unresolved energy region physically, at the boundaries, the parameters of the resonances locatedabove the boundary of the "resolved energy region" are added if possible. Or
more often, the "background cross sections" are given properly to the corresponding interval at the boundary, similarly to other boundaries.
The unresolved resonance parameters are estimated based on the resolved
parameters then checked and adjusted to fit the newly measured point—wise data (if any) in the unresolved resonance energy region.
So CENDL-2 is much more improved comparing the CENDL-1. And it
seems that most of the evaluations included in CENDL—2 are comparable tothe corresponding files of the available newest versions of other evaluated nuclear data libraries.
Compared with newest evaluated data ENDF / B—6 and JENDL—3, thenuclides and files of CENDL—2 are much less than ENDF/B—6 andJENDL—3. Comparings show that the data for most nuclides, which are included in all CENDL-2, ENDF / B-6 and / or JENDL-3, agree with eachother within experimental error, and some are considerably different. For example, the double differential cross sections of D(n,2n) neutrons are given systematically in CENDL—2, which were calculated with Faddeev equation andthe results are consistent with experimental data quite well (Fig. 1). Compared
to ENDF / B—6, the cross section of inelastic scattering to 4.63 MeV levelfor 7Li is considerably lower, this is based on newly measured data, in which
the correction to D—D break—up neutron was made. For structural materials,
some examples are the cross section of Ni(n,a), Cr(n,2n) and (n,a), Ta(n,2n) and(n,3n), Nb(n,a) reactions, they are shown in Fig. 2~6. For fission nuclides, thecomparison with ENDF / B-6 of ^ P u fission cross section is shown in Fig. 7,
they are consistent with each other within 4%. The examples of the differences
are the cross sections of 238U(n,n/), and 239Pu(n,2n) (Fig. 8, 9).
1.1.2 Preparations for further improvement of CENDL
Only files 1 —- 5 have been included in CENDL—2. So in recent years much
effort has also been paid to the preparations for further improvement of
CENDL—2, mainly to include the files of y-production data, double differential
cross section (DDX), and covariance file, etc.. Correspondingly, a code UNF
which is able to calculate the DDX of neutron and charged particles emission as
well as recoil nuclei, to calculate the data of y—production concerned, etc. based

Annex 4 . 4(cont.)

on a more perfect model theory framework; and a code system for combining
the correlated data sets to obtain combined (evaluated) values and theircovariances correctly and reasonably have been developed, these codes havebeen used to do some calculations and evaluations successfully. Furthermore,
for improving the evaluations of averaged resonance parameters, especially theaverage level spacing and the level density, a method based on Bayesian approach for correcting the energy level missing related to not only thePorter—Thomas distribution but also the Wigner distribution has been advanced and a code correspondingly have been developed.
In the meantime, we have taken part in the international cooperation of
FENDL improvement and the related activities. Undoubtedly, these activities
will be very helpful to the further improvement of CENDL.
1.2

Nuclear Data for Special Purposesa) Nuclear Structure and Decay Data (NSDD)All useful ENSDF codes have been transplanted on MICRO-VAX-II
computer of CNDC. The data for A = 51-55, 195-198, 170,172 (total of 12
mass chains) have been evaluated and renew of some mass chains started in
1990.
b) Fission Product Yield Data (FPYD)
The Chinese Evaluated Fission-Product Yield Library has been established. The 1987 version of this library contains data in ENDF / B—5 format
for 10 fissioning systems, they are U235T, U235F, U235HE, U238F, U238HE,
Pu239T, Pu239F, Pu241T, U233T, Th232F. (T-thermal neutron, F-fast (fission) neutron, HE—14 MeV neutron). The data library on magnetic tape isavailable from the IAEA / NDS.
At present, the efforts is being paid to obtain an improved and more complete data base of experimental data in EXFOR format and study the methods
to derive a best recommended set of fission yield data, which aim at update the1987 version data.
Besides, the "decay heat production" research has been developed in recent
years.
c) Charged Particle Nuclear Data (CPND). The twenty sets of data measured in China have been compiled in
EXFOR format and sent to IAEA. The 220 sets of measured data (50-1000
MeV) for the reactions induced by proton or heavy charged particles were compiled in EXFOR format cooperated with BNL / NNDC. Some activation crosssections induced by charged particles are being evaluated.
. Nuclear data of proton induced reaction at the energy region of 4 ~ 50

MeV, including 1 ~ 4 particle emission have been calculated for p+ 89 Y by using
CMUP2 with the code APCOM.
d) Neutron Activation and Dosimetry Reaction Data
Combined with measurements (77 reaction channels), the cross sections of(n,y), (n,n'), (n,2n), (n,3ri), (n,p), (n,t), (n,a) for 55 reaction channels have been
evaluated. « Compilation of Evaluation for Activation Cross Section))-CNDC-89014, INDC (CPR)-16 has been published.
The following reactions have been evaluated in an IAEA contract subject(5516 / RI / RB): 23Na, 45Sc, 58Fe, 59Co, l09 Ag(n ,y);4M7
Ti(n,p), N Ti(n,x); 54 Fe, 59 Co(n,a); 55 Mn, 59 Co, 115 In, 127 I, l81 Ta(n,2n)
and n 5 In(n,n0. The complete evaluated dosimetry file including a pointwisecross section and covariance file in ENDF / B—6 format with the minidisk aswell as evaluated reports have been sent to IAEA.
e) Photo—Nuclear Reaction Data
The <ryn for D, Be, 75As, 95Zr and 127I have been reevaluated. Together
with the EXFOR entries, they have been sent to IAEA.
f) Atomic and Molecular (A+M) Data
The sputtering data for collisions of C, Al, Fe atoms and their ions with H,
D, He atoms are being compiled and evaluated. The excitation cross sections ofcollision for He, Ne, Ar atoms with their ions, the electron impact ionization
cross sections for the atoms and ions with high Z and the cross section for
K—shell ionization by electron impact are also being compiled.
g) Medium Energy Nuclear Data
Several studies on medium energy nuclear data calculation and evaluation
have been done recently. The subjects are : 1. Calculation of 5 ~ 50 MeV
neutron induced reaction data of 56Fe; 2. The study of neutron emissions in
585 MeV proton on 56Fe with Quantum Molecular Dynamics; 3. Neutron
relativistic phenomenological and microscopic optical potential; 4. Systematics
of intermediate energy proton nonelastic and neutron total cross section.

Evaluation Method Research*1'2'4" 1419~251

2

The three aspects evaluation methods were usually used to generate theevaluated d a t a :. combine and fit available measured data by using least squares method;. predict cross section by systematics;. carry out a consistent theory calculation;
The related codes have been or are being developed.
2.1

Data ProcessingMethod[4'5I9~21'251— 4 —Annex 4 . 4(cont.)— Correlated Data Combination and Covariance Evaluationa) Covariance matrix construction for experimental data using the information about errors in experiments given by authors.
b) Curve fitting The least squares codes based on polynomials,
orthogonal polynomials, Legendre polynomial and B—spline, have been developed previously for curve fitting and used to combine the data ofmulti—measurements to obtain the evaluated excitation functions. A spline fitting program for multi-sets of data has been developed. With which the knots
can be optimized, spline order number can be chosen, the correlative data canbe fitted and the covariance matrix of the fit values can be calculated. Also auniversal code is developed. The functions include single parameter combination, curve fitting by using orthogonal Polynomial and Legendre Polynomial asbase.
c) Simultaneous evaluation Based on spline fitting for multi—curves andBayes method, several relative reaction cross sections and their ratios for different nuclides, or all reaction cross sections of a nuclide are fitted simultaneously.
As a result, they are made consistent with each other, and the correlation between different reactions and nuclides can be calculated.
d) PPP in correlated data combination and the ways to solve it
When the least squares method are used to combine the correlated data,sometimes the combined values are outside all of the measured values. Obviously it is unresonable and unacceptable. This phenomenon is proposed by R. W.
Peelle as "Peelle's Pertinent Puzzle (PPP)". The description in detail of ppp anda way to solve it as well as the methods to deal with it approximately in practise
are included in some reportst25] to be published.
The approximate methods have been adopted in the codes GAFC. TPFC,
and MPFC for correlated data combination.
e) A code of transforming neutron and charged particle emission datafrom ENDF/B-4,5,6 format into DDX or EDX and plotting have been
written.
2.2 Systematics Studies
Systematics studies on the excitation functions of the (n,y), (n,2n), (n,3n) as
well as (n,x) (x = p,d,t and 3>4He) reactions have been performed. The
parameterized formulae and all the parameters concerned have been obtainedon the basis of the evaporation model with the preequilibrium mechanism andthe collected data for A = 25—200 in the neutron energy range from threshold to
25 MeV.
With the formulae and parameters, the excitation functions could be pre-dieted simply for the energy regions or nuclides not measured heretofore andthe formulae have been used for curve fitting in case the measured data arescarce.
2.3

Nuclear Data Calculation and Nuclear Theory Research ll ' 2>6 ~ 14 ' 19 ~ 24]

In recent years, our theoretical research on the nuclear reaction theory,calculation method and parameter and computer codes has been advanced greatly
which are as follows :a. Semi—classical theory of multi-step nuclear reaction processes1221
The semi—classical model of multi-step direct and compound reactions has
been developed. In this model, the pre-equilibrium reaction processes can be
described by a unified approach with the angular momentum and the parity
conservation without any ansatz. The exciton transition rate in J—Pai dependent and the mean lifetime of the exciton state dependent on the angular momentum by solving the J-Pai dependent master equation exactly were obtained.
In this theory, the Pauli exclusion effect is considered in the exciton state density. For composite particle emissions, the pick—up mechanism has been adopted
and the formation factors of the heavier composite particles have been derived.
With the leading particle model, DDX of all kinds of emitted particles can becalculated.
Based on this model the code UNF has been set up.
b. Non-relativistic and relativistic phenomenological and microscopic
optical potentials for neutron induced reactions at low and medium energies'23'
Non—relativistic and relativistic phenomenological and microscpic opticalpotentials are studied and compared for neutron induced reactions at low andmedium energies. The calculated results show that the microscopic optical potential based on generalized and modified Skyrme force (GS2 and Ska), which
has an analytical formalism without any free parameters, is useful in nuclear data calcualtion and evaluation. The global neutron relativistic phenomenological
optical potential based on the available experimental data for various nuclei
ranging from C to U with incident energies 20 ~ 1000 MeV has been obtained
through automatic search of the best parameters. The nucleon relativistic microscopic optical potential is studied by utilizing effective Lagrangian based on
Popular Walecka model, through extensive comparisons we can understand theneutron optical potential in large range of energy quite well.
c. Dispersion optical potential'8'
A review of optical model analyses in A = 40-60 mass region is giv_en andthe variation of the total cross section, the elastic scattering angular distribution
and the absorption cross section with the optical potential parameters is6

Annex 4 . 4(cont.)

studied. The comparative analyses of different parameterizations of the spherical optical potential have shown that a deep minimum in the total cross section
at low energies cannot be reproduced by any existing parameterizations. These
optical potentials which fit the higher energy data, very accurately tend to give
total cross sections at low energies that are clearly greater than the mean of thefluctuating experimental values. We show that a consistent analyses using thedispersion relations remove this "anomaly" of the total cross sections at low energy.
d. Nuclear level density181
Although the Gilbert—Cameron (GC) formula is rather universal in theapplication of the statistical theory, its constant temperature formula at low energy range is from an empirical approach without theoretical guidance, and thespin cut-off factor for the constant temperature formula is not well-definedand disagree with the experimental data either. Compared to GC formula, theproblem mentioned above does not exist in the back—shifted Fermi gas model(BS formula), but its parameter form is not as universal as GC formula. The
reasonable parts have been extracted from both formulas and combined them
together. First of all, the level density parameters a and V values of BS formulafor 318 nuclei have been obtained by fitting the evaluated experimental data.
The spin cut-off factor at low energy region for BS formula has been improved.
The systematics study of the parameters a has been carried out. The system atics
results of S(Z) and S(N) have been obtained.
e. Radiative neutron capture1201
Three nonstatistical effects, the capture in shape elastic, compound elastic
and compound inelastic channels, have been studied[11]. The research shows thatthe contributions of some nonstatistical effects must be taken into accountcarefully even if the incident neutron energy is smaller than 3 MeV.
Nonstatistical effects lead to an improvement of the gamma emission spectrum
in high energy region.
The theory research for light nuclides
By using phase shift analysis, the calculations of n—H, n—D and n—T scattering cross sections have been carried out. The results are in agreement withexperimental data.
The double differential cross sections for n+D have been calculated withsolving Faddeev equationf12l A set of low rank separable nucleon—nucleon potentials has been constructed, which includes different partial waves and tensor
force. The calculated results are in good agreement with experimental data. The
results also show that the contribution from off—shell effect is more significant
than those from three body force and relativistic correlation.

On the basis of theory research mentioned above, some codes for the nuclear data calculations have been developed. Some of them have been sent to
NEA Data Bank. Main ones[2I] are :. MUP2 MUP2[9>10] is the second version of a unified program for theoretical calculation of fast neutron data for medium—heavy nuclei by using theoptical model, Hauser-Feshbach theory with width fluctuation correction(WHF) and pre—equilibrium (PE) statistical theory based on the exciton modeland evaporation model. With AUJP, an associated code of MUP2 used for automatically searching of optimal optical potential parameters. MUP2 has beenused in the evaluations for CENDL—2, and compared with international nuclear model programs.
. CMPU2 Based on MUP2, for calculation of charged particle as well as
neutron induced reactions at the energy region of 4 ~ 50 MeV, including 1 ~ 4
particle emission. With the codes APCOM and APNOM used to search the
optimal optical potential parameters, CMUP2 has been used to calcuate the data sets of p+89Y and n+56Fe reactions, the incident energy from 4 to 50 MeV.
. MUP3 MUP3 lll] code is developed recently which is an extend code of
MUP2 to calculate the double differential cross section for secondary particles
and to deal with composite particle emission.
. FUP1 FUP1 is an extended code of MUP2 for fission nuclides calculation. With ASOP and ASFP, the associated codes of FUP1 used to automatically search for optimal fission and optical potential parameters respectively.
. CCOM A code of coupling channel optical model for deformed nucleus
to calculate the direct reaction components of the inelastic scattering for 3 isolated levels of the residual nucleus. These direct components are added to thecalculated compound nucleus cross section and angular distribution.
. UNF Developed recently for structural material calcualtion with theunified treatment of the pre—equilibrium and equilibrium reaction processes
with angular momentum and parity conservations. The pick—up mechanism ofcomplex particle (d, t, 3He, 4He) emission and the discrete level effects aretaken into account for improving the calculations of reaction cross sections
concerned. It is able to calculate DDX of particles emission as well as recoil
nuclei, and y—production data. With other codes for optimal optical parametersand direct components complement, UNF has been used to calculate the data
sets of n+56Fe, n+209Bi reactions
Some codes have been developed for light nuclides :. TSD TSD is based on solving the Faddeev equation for n+D reaction.
. ROP is a unified code of optical model and R matrix theory;. CROP is able to fit simultaneously the experimental data of both a reac— 8—

Annex 4.4(cont.)

tion and the corresponding inverse reaction in a system;. DRM is a unified code1131 for calculating direct inelastic scattering crosssection for IP shell nuclei with optical model and DWBA.
These codes have been used to improve the evaluations for 6'7Li.
. RAC A comprehensive R-matrix analysis code based on multichannel
and multilevel R—matrix theory. It has been used to analyse the 7Li and l7O
systems to evaluate the data of n+6Li (En < 1.72 MeV) and n+16O (En < 6.2
MeV) reactions respectively.
. In the study of the three—body breaking up reactions, the code for thequasi—free particle scattering was developed to calculate the integral cross sections, DDX and normalization factor at any angular momentum.
Recently, CNDC is engaged in the compilation, evaluation and theoretical calculation for intermediate energy nuclear data (IEND)^14>23]. Based on
our investigation, the nuclear reaction theories which can be easily andrealistically used to calculate IEND are as follows : relativistic optical model;
relativistic collective deformed DWBA approach; intranuclear cascade modeland hybrid-type preequilibrium model. Some microscopic theories for IEND
calculation have also been researched. Both the phenomenological and microscopic nucleon relativistic optical potentials are presented. The global neutron
relativistic phenomenological optical potential (RPOP) based on the available
experimental data for various nuclei ranging from C to U with incident energies
En = 20—1000 MeV has been obtained through automatically searching for the
optimal parameters. The nucleon relativistic microscopic optical potential(RMOP) is studied by using effective lagrangian based on popular Walecka
model. Through comparison between the theoretical results and experimental
data, some insight into both the RMOP and RPOP have been obtained. It isshown that the calculated results of the microscopic relativistic optical potential
at the nucleon energy range 20~ 1000 MeV over a wide nucleus region are in
reasonable agreement with experimental data without any adjustableparameters.
The evaluation of 56Fe(p,n) experimental cross sections (Ep = threshold-1000 MeV) have been finished.

3

Multigroup Constant Generating and Benchmark Testing[1'2>15~17]

To meet the urgent needs in nuclear engineering, since 1986 large amountof the nuclear data for nuclear power, nuclear safety analysis and nuclear engineering design have been processed. Through international exchange, some valuable codes have been obtained from ORNL/ RSIC, A N L / NESC and NEA— 9—

Data Bank, and based on them, a few of program systems used for data processing and reactor calcuations have been established. Now we can provide thecodes and data for the nuclear science and engineering.
1) Three program systems of group constant generating have been implemented on computer CYBER-825 at CIAE. These codes are AMPX-II,NJOY and MINX which are used in data processing for nuclear science andtechnology.
2) PASC-1 [16] was made based on AMPX-II in cooperation with ECN(Holland). It is composed of AMPX / SCALE group constant module, severaltransport calculation codes Sn and 1—3 dimension diffusion code CITATION.
PASC—1, has been sent to NEADB. This code can be used in the design of reactors. A library including 45 and 52 group constants of 37 nuclides has been processed by PASC—1 for the fast reactor calculations. A multigroup Monte—Carlocode KENO-IV from RSIC has been linked to the code system PASC-1. Going through large amount of benchmark calculations, it has been proved that
the AMPX—KENO-IV is reliable to use it in critical safety analysis. Therefore
it has been applied to the critical safety calculations of the high—density
spent—fuel storage racks at the Qinshan nuclear power station.
3) Based on BINX and CINX, the CCCCPS code system1 !5) , which is
automatized, has been made for processing the interface file of CCCC format
library. By using the CCCCPS code system, the 50 group constants of 49
nuclides from LIB-IV CCCC library were processed into 46 group ABBN library in the Bondarenko format for the input of the code 1DX for the fast reactor design.
4) The FRBT code system is composed of three codes EXDL, BRKP and
NDP, and an integral experiment data library included 19 fast benchmark assemblies. The material compositions, geometric conditions and the other controlled variables about 19 assemblies recommended by American CSEWG havebeen included in the library. The EXDL is a code to retrieve an interface file forcalculating a reactor by NDP. The BRKP is able to retrieve an interface file ofthe multigroup constants in the Bondarenko format from the ABBN library.
NDP is an one-dimension diffusion code used in critical calculations of reactors. The user's input of the FRBT is very simple and inputing one of the numbers to be arranged in order of assemblies is only required. Using the FRBT
code system with the ABBN library of 46 groups, the calculations about 14 fastcritical benchmark assemblies have been finished. The results are consistent
with those given by CSEWG.
5) The theoretical analysis for Be sphere shell neutron multiplication factor is also carried out. This is a cooperation project with U.S.A. and Japan.
— 10 —

Annex 4 . 4(cont.)

In cooperation with ECN (Holland), the ECNJEF-1 Library1171 was set up
by using NJOY-87.0, CRECTJ5, MILER, NPTXS and XLACS-2. The
ECNJEF-1 Library is a 219 neutron group Library from JEF-1 in the AMPX
master format. 16 files are included in this Library with 434 elements. Some
problems in JEF—1 and related processing codes were met. Most of the themwere solved. MILER-ECN version was sent to NEA Data Bank by ECN.
Now we can make the benchmark testing for the nuclear data and provide
various multi—group constants for the calculations in thermal reactor, fast reactor and fission—fusion reactor and for shielding calculations.

4Construction of Nuclear Data Library and Related
Program Library, Management, and Service11 ~3>18~211

A group in CNDC is responsible for the nuclear data library and the associated program library. At present, the group has the following main tasks :. to prepare and maintain the Chinese Evaluated Nuclear Data Library(CENDL).
. to get experimental and evaluated nuclear data and computer programsfrom abroad through exchange.
. to improve or develop the library management, data processing andevaluation program systems.
. to compile the data measured in China in EXFOR format.
. to collect, compile and evaluate atomic and molecular data and establish
such a data library in cooperation with the atomic and molecular data working
group.
. to provide nuclear data and program services to Chinese users and exchange them with IAEA / NDS and other centers.
. to operate, maintain and manage the computer.
Now, the PDP 11 / 70 and MICRO-VAX-II computers are operated andused in data evaluations, data calculations and library construction
successfully; The E N D F / B - 6 and EXFOR code systems ( including the
ENDF utility programs, version 6.6 ) have been transplanted onto
MICRO-VAX-II, so neutron data in EXFOR and data files in ENDF / B4-6
format can be processed; We have set up a complete program systems for nuclear data evaluation and library management.
Development of the code library. Following codes have been stored
and / or checked or assessed : 30 codes made by ourselves, ~ 60 codes, used innuclear engineering, obtained from RSIC (U.S.A.), ~ 100 codes obtained fromNEADB (OECD). So far more than 100 codes have been used by the home users.
— 11 —

References
[I]
[2]
[3]
[4]
[5]
[6]

Cai Dunjiu et al., INDC (CPR)-Ol 1 / GI, p9-32(1988).
Cai Dunjiu et al., Communication of Nuclear Data Progress (CNDP), No. 1,6(1989).
Cai Dunjiu et al., CENDL-1, CNDC-85010,1986.
Zhou Delin et al., CNDC-85013,1986
Liu Tingjin et al., CNDP, No. 2, 58(1989).
CNDC hsj 78211-78246(1980) The Selected works on Nuclear Reaction Theories
and it's Applications.
[7] Wang Shunuan, CNDP, No. 3, 32(1990).
[8] Su Zongdi et al., Study of nuclear level density for Fermi gas model, Progess Report(1988-1989), p33, Beijing National Tandem Accelerator Laboratory, CIAE (1990);
J. Phys. G : Nucl. Phys. 14,1485 (1988).
[9] Cai Chonghai et al., CNDP, No. 3, 26-31 (1990).
[10] Su Zongdi et al., Chinese Journal of Nucl. Phys. (CJNP), 11,4,41 (1989).
[II] Yu Ziqiang et al., CNDP, No. 1,41 (1989) & No. 2,9 (1989).
[12] Chu Lianyuan et al., CNDP, No. 5,14(1991).
[13] Zhu Yaoyin et al., CNDP, No. 1, 29 (1989).
[14] Shen Qingbiao et al., INDC (NDS)-245, IAEA Advisory Group Meeting on Intermediate Energy Nuclear Data for Applications, Vienna, Austria, 9 ~ 12 Oct., 1990, pl29
and pl41.
[15] Liu Guisheng, CNDP, No. 1, 78 (1989).
[16] Wang Yaoqing, J. Oppe et al., ECN-89-005 (1989); CNDP, No. 3, 58 (1990).
[17] Yu Peihua, H. Gruppelaar et al., NFA-LWR-90-02 & 03 (1990); ECN-89-112 (89).
[18] Liang Qichang et al., CNDP, No. 3, 56 (1990).
[19] Cai Dunjiu, NEANDC (J)-160/U, Proceedings of the 1990 Symposium on Nuclear
Data, p7~35.
[20] Liu Tingjin et al., Proceedings of the International Conference on Nuclear Data for
Science and Technology, 13~ 17 May, 1991, Juhch, Germany.
[21] Cai Dunjiu et al., Proceedings of the Beijing International Symposium on Fast
Neutron Physics, Beijing, Sept. 9 ~ 13,1991.
[22] Zhang Jingshang, Semi-Classical Multi-step Reaction Theory and its Applications,ibid.
[23] Shen Qingbiao, Comparison of non—relativistic and relativistic, phenomenological andmacroscopic optical potentials for neutron induced reaction at low and medium energies, ibid.
[24] Su Zongdi, CNDP, No. 5,19(1991).
[25] Zhao Zhixiang, The Covariance Matrix of Derived Quantities and Their Combination,
to be published.
— 12 —

Annex 4 . 4(cont.)

Fig. 1 D(r»,2n) Double
Differential Cross Section
at 9 = 25°,
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LAS Auchamp(77)Annex 4.5

The Activities on CENDL, EXFOR, CINDA and WRENDA in China
Liang Qichang
Chinese Nuclear Data Center
Institute of Atomic Energy
P.O. Box 275 (41), Beijing, P.R. China
The main nuclear data activities in China have been reported by Dr. Cai Dunjiu,
Director of Chinese Nuclear Data Center, in this Meeting111. In this article, we merely givesome supplement on several aspects, i.e. CENDL-2, EXFOR, CINDA, and WRENDA.

1.

CENDL-2 and relative programs system

The Chinese Nuclear Data Center and Nuclear Data Committee of China started
evaluation and compilation work for CENDL-2 in the beginning of 1986. The main purpose
for making CENDL-2 is to develop and improve the CENDL-l12-31, such as to extend theincident neutron energy to thermal energy region, supplement the data type of evaluations,improve and update the earlier evaluations, and add some new evaluations to the library.
CENDL-2 was finally completed in July 1991; it contains data for main engineering,
construction and fuel materials in nuclear reactors, radiation shielding materials and so on.
The CENDL-2 was based on the CENDL-1. 54 nuclides in all are included in thisversion, as shown in Table 1. Of these, 36 nuclides are from CENDL-1, but have been reevaluated or extensively revised around the years 1989/1990. The rest (Va) were newly
evaluated. All evaluations were performed by Chinese evaluators of CNDC and Chinese
Nuclear Data Coordination Network (CNDCN) except that a few ones were completed by
Chinese evaluators at home or abroad for foreign libraries via international cooperation andthese evaluations are also included in CENDL-2. Some evaluations are based on existing
foreign libraries, such as ENDF/B-6, JENDL-3 and BROND, with partial updates andrevisions performed by Chinese evaluators.

Table 1. Nuclides Contained in CENDL-2
JH, 2 H, 3 H, 3 He, 4 He, 6Li, 7Li, 9Be, 10B, n B, 14N, !6 O, 19F, 3 N a , Mg, 27A1, Si, 31 P, S, K,
Ca, Zn, Ti, 51V, Cr, 55Mn, Fe, 59Co, Ni, Cu, Zr, 93Nb, Mo, Ag, lff7Ag, 109Ag, Cd, In, Sn,
Sb, Hf, Ta, W, 197Au, Pb, 232Th, 235U, 238U, 237Np, 239Pu, 248Pu, 241Am, 249Bk, 249Cf.

The library contains full sets of neutron data, i.e. resonance parameters in the resonanceregion and cross sections of all reactions, energy and angular distribution of secondary
neutrons, and for some evaluations also double differential cross sections or 7-production

-2data, in the energy range from 1O"5 eV to 20 MeV. Most of the evaluations are presented
in the ENDF-5 format, some in ENDF-6 which contains double-differential cross section orReich-Moore resonance parameters in resolved resonance region, which are not permitted
in ENDF-5 format.
All the evaluations were carefully checked and reviewed by Chinese specialists. The
Chinese Nuclear Data Center also organized a collective examination carried out by
specialists from various institutes and universities. Finally, all the evaluations were checked
through by CHECKR, PSYCHE, FIZCON and then accepted by CENDL-2.
More detailed descriptions of CENDL-2 and the evaluations contained in CENDL-2 aregiven in elsewhere14'51.
In order to manage the library, the ENDF data base system, i.e. the storage and retrieval
system, developed at NNDC, U.S.A. has been installed in Micro-VAX-II computer at
CNDC.
The ENDF Utility codes, version 6.6 from NNDC have also been transplanted on
Micro-VAX-II computer and used for checking and processing evaluated neutron data for
CENDL-2.
A code CRECTJ5 developed at JAERI/NDC has been transplanted to Micro-VAX-II
computer, this code has functions of reading evaluated nuclear data and making a complete
file of them. In addition to such fundamental functions, it has also useful functions ofarithmetic operation of cross-section data, averaging of cross sections, correction of data,
construction of natural element data from its isotope data and so on. This code has beenused for evaluation and compilation work of CENDL-2.
Now the CENDL-2, ENDF/B-6, JENDL-2 and BROND libraries have been loaded indisk of VAX-II and serves the users in China.

2.

EXFOR

According to the research contract to IAEA, in recent years, many efforts have been
made to develop the EXFOR software system for nuclear data compilation and to compile
the EXFOR nuclear data measured in China. Now the EXFOR software system, which
includes three parts, i.e. Edition, Check, and Retrieval, has been completed basically andused in the EXFOR data compilation.
Another "PC software assisting the nuclear data compilation in EXFOR" developed by
Dr. V. Osorio has also been transplanted to our 386 PC.
The EXFOR processing program system and Storage and Retrieval system developedby NNDC have also been installed in Micro-VAX-II computer under the assistance of IAEA
expert Dr. C. Dunford.

Annex 4.5(cont. )-3So now the conditions for EXFOR nuclear data compilation and management in CNDC
is quite good.
The main purpose of EXFOR work in CNDC is the data compilation itself, and it will
be a long-term task, because IAEA/NDS no longer compile in EXFOR Chinese data since1988. Up to now, we have compiled 10 EXFOR entries and sent them to IAEA/NDS in
1989, 1990 respectively, another 5 EXFOR entries will be compiled and sent to IAEA/NDS
by the end of 1991, and we plan to compile at least 20 EXFOR entries in the coming year.
In order to coordinate the activity on EXFOR nuclear data compilation in China, theNetwork for EXFOR data compilation has been established last year. The Network consistsof several institutes and universities in China. Unfortunately, the scientists of the network
are not familiar with EXFOR field, so they have spent much time to be familiar with thismatter in the past two years, and the EXFOR data compilation work was a little delayed.
In the EXFOR data service, we hope that the entire EXFOR data library will be suppliedby IAEA/NDS and loaded in our Micro-VAX-II computer when the new hard disk provided
by IAEA is installed.

3.

CINDA

Up to now, the CINDA work has not been carried out systematically in CNDC, although
we have compiled some CINDA entries in the past several years. We hope that this work
will be continued hereafter.
Besides, IAEA/NDS has sent us the entire CINDA library and related codes system, we
also hope we could build and maintain the CINDA library in Micro-VAX-II computer infuture.

4.

WRENDA

The WRENDA work was started in CNDC in 1987. We have collected some nuclear
data requests in China and compiled the requests list for inclusion in WRENDA 87/88 at thattime. According to the requirement of IAEA/NDS, we are now starting the preparatory
work for WRENDA 91/92, the main tasks are as follows:(1)

To ask previous requestors to review, update and make necessary changes on theirprevious nuclear data requests, or to delete the previous requests if they aresatisfied by recent work or no longer needed.

(2)

To collect new requests, check and review them, fill in request form and thensubmit to IAEA/NDS.

-4-

5.

Proposal for ENDF format modification(1)

The theoretical and evaluation scientists feel that the highest order Legendre
polynomial NL < 20 is not enough to describe the angular distribution of secondary
neutron for medium-heavy nuclides in the higher energy region. It is appropriate
to increase the NL up to <30.

(2)

The requirement for giving the angular and energy distribution of secondary
neutrons from the first, second, third and fourth-chance fission (i.e. MF=4,5
MT=19,20,21,38) are not necessary even when their cross sections have been
given in M F = 3 , because their average number of neutrons released by thesechance are not given in MF=1 correspondingly. So we would like to proposethat:- no longer require to give the MF=4,5 MT= 19,20,21,38 in evaluation even when
their cross section are given in MF=3; or- to give the average number of neutrons released by these chance fission incorresponding section (MT) in M F = 1 , when the MF=3,4,5 MT= 19,20,21,38 aregiven in the evaluations.

References[1] Cai Dunjiu, Progress of Nuclear Data Work in China (1991).
[2] Liang Qichang et al., Chinese Evaluated Nuclear Data Library (CENDL),
IAEA-NDS-61 (1985).
[3] Chinese Evaluated Nuclear Data Library, Version 1 (CENDL-1), Edited by CNDC,
1986 (in Chinese).
[4] Liang Qichang et al., Chinese Evaluated Nuclear Data Library, Version 2, (CENDL-2),
1991.
[5] Communication of Nuclear Data Progress No. 6, special issue for CENDL-2, Edited by
CNDC (to be published).

Annex 4 . 6

DATA ACTIVITIES IN RIKEN NUCLEAR DATA GROUP
Status Reportto theEleventh Meeting of the Nuclear Reaction Data Centers
Obninsk, October 7 - 1 1 , 1991
Y. Tendow

1) Staff
There were some changes in the staff of RIKEN Nuclear Data Group
this year. A.Hashizume retired from RIKEN and moved to anotherorganization. He still renains in the group as a part-time member and is
supposed to continue the nuclear data compilation works. Y.Tendow has
succeeded him as the person in charge. In addition to EXFOR, we also arein charge of compilation of ENSDF and Nuclear Structure Reference file
(NSR) for secondary sources originated in Japan. So, any decrease in theproper staff would lead to a constant shortage of manpower. From longterm pointof view, it is an important matter to obtain new members in thegroup.

2)

1
1

Permanent,

EXFOR, ENSDF, NSR.

Concurrent,

EXFOR.

1

Concurrent,

Computer.

2

Part-time,

EXFOR, ENSDF.

1

Assistant,

EXFOR, ENSDF, NSR.

Computers

Nuclear Data Group belongs to the Radiation Laboratory in the Main
Research Building. The central mainframe computer FACOM M780 (which
will soon be upgraded to FACOM Ml800 256 MB memories, 120 GB disks,
400 GB MT library) is running under double operating systems, MSP (IBMcompatible) and UTS (UNIX). We are using the mainframe for thecompilation works, and also several PCs linked to the mainframe and othernetworks. PC's mainly used are as follows:FUJITSU FM-R70, terminal of the mainframe. 40 MB HD.
IBM PS/5530 (equivalent to PS/2). 40 MB HD, math.co-processor.
NEC PC-9801. 120 MB HD, math.co-processor.
Macintoshes and other NEC PC's.
In the RIKEN Acceleraror Facility area, another computer network(FACOM M38O, VAX6510, VAX8350, uVAXII's etc.) is running under
DECnet / TCP/IP protocol. It is also connected to the Main Building
network with optical cables. Although we can access and remote login tothese computers, we are not yet using them for data compilation works at the
moment. We can exchange E-mail through the BITNET, and can remotelogin to overseas computers through the Internet or HEPNET etc.
3)

EXFOR

We have been continuing to collect cross section data restricting to 20
isotopes of medical use. Most of them are already incorporated into EXFOR
file but not a small number of important works are left untouched. To coverthese missing works as well as recent ones is essential for the completeness of
EXFOR file. We have just sent the trans tape R006 to NDS which contains
4 entries with a total of 41 subentries of excitation functions.
4)

ENSDF, NSR

The mass-chain evaluation and compilation for A = 177 is in progress
suffering a considerable delay. Another mass-chain evaluation for A = 129
has just started. NSR file compilation for 1988 and 1989 secondary sourcesof Japanese origin has completed with some delay. The file is just to be sentto NNDC. We have started on the compilation for 1990 secondary sources.

Annex 4.6(cont.)

Ethernet cable routing at RIKEN
Main Research building

Accelerator,''*

Facility

Ring Cyclotron

\

2F
500m

5F
4F

500 m

Radiation Lab.

t

500m

2F
1F

300m
500m

[NMCj

3F

BF

|B

/Optical cable

V ^TCP/IP

(R)

C

c

500m

DECnet (TCP/IP)^yBuffered Repeater(repeat all the packets)n r i Data link Bridge'—' (repeat only crossing packets)
500m(O) Opticaltranceiver

TCP/IP

Frontier Lab. Building[NMC] Network Management consoleAnnex 4 . 7

Status Report of SG to the 1991 NRDC Meeting

Japan Charged-Particle Nuclear Reaction Data Groupe
M. Chiba

Sapporo Gakuin University
Bunkyodai-11, Ebetsu, Hokkaido, 069, Japan

CPND compiling with NRDF
CPND compiling with NRDF format has been continuing since 1980. 46 and 59
entries have been added in 1989 and 1990, respectively. By March 1991, thetotal amount of compiled data have reached 52 MB, 1100 entries. The newly
compiled entries in 1989 and 1990 are the ones that were almost all produced inJapan.

Into EXFOR translation
In 1990 we submitted to NDS two TRANS tapes: E007 and E008. But TRANS E007
is a revised retransmission of entries in TRANS E005 and E006 to eliminate
mistakes found. E008 contains 8 entries which are selected from the NRDF datacompiled in 1989.
In 1991, TRANS E009 was submitted to NDS. This TRANS contains 19 entries.
These are converted from the entries compiled in 1990.

NRDF ANNUAL REPORTOur activities has been reported since 1987 by "NRDF ANNUAL REPORT" whichis written in Japanese. This report is distributed among reserchers in therelated fields in Japan.
Main topic of "NRDF ANNUAL REPORT 89" is on the result of questionaire- 1-

survey to the potential users about NRDF activities. This survey positively
showed that many authors of data would cooperate with NRDF in direct dataacquisition from the author or author proof. So we are now under deliberationof inventing soae Beans to get authors' cooperation of data.
In "NRDF ANUAL REPORT 90", index lists of the NRDF entries and translated
EXFOR entries appeared. Titles and author's names of the entries compiled in
1990-are also listed.

Computer Facility
We utilize the Hokkaido University Computing Center for the storage andretrieval of NRDF and EXFOR information. The Hokkaido University Computing
Center installs Hitachi M-682H and S-820/80 computers. These computers areconnected to the National Academic Information Network. So Researchers of theuniversities or colleges in Japan can access our NRDF or EXFOR information
through the Network.
For NRDF data compiling and graph data reading, we also utilize several
PC's with a digitizer.

-2-Annex 4.7(cont.)

5 0

ANGL-DSTRN

Contents of
NRDF

66.9 %DSIGMA/DOMEGA 60.5
ANALPW

27.5

ENGY-SPEC

24.0

XSECTN

22.3

OPT-POL-PARA

18.0

EXC-FUNCT

17.6

SPIN

17.1

PTY

16.5

EXC-ENGY

16.4

Annex

4.8

NEA DATA BANK Progress Reportto the NRDC Meeting in Obninsk/Moscow, October 1991

INTRODUCTION
The demand on the Data Bank services has recently been very high. Computer program requests haveincreased 20 percent when compared with the last few years and the nuclear data requests by about 50
percent. The last value could be explained by the fact that new versions of the three major evaluatedlibraries were released in 1990. The work on the Thermochemical Data base (TDB) continued asplanned and the report on the uranium elements was sent out for final review with the aim to be
published at the end of 1991.
The cooperative arrangement between US DOE and the NEA concerning nuclear data and computer
program exchange was provisionally prolonged until September 1991. The nine months prolongation
was requested from US DOE to finalize the arrangement covering a longer period of time.

COMPUTER PROGRAM SERVICES
Testing and Masterfiling
In all 110 new computer code packages were master-filed in 1990. Ninety percent were fully tested while
the others were only screened for completeness and correct syntax. The large turnover of staff together
with vacancies during the year have further increased the backlog of programs available but not yet
tested at the Data Bank
An increasing amount of software designed to be operated on personal computers is acquired every
year. The programs running on personal computers amount to about 150 (about 10% of the total) This
software is checked as to whether it contains one of the known viruses. For the purpose standard
software has been acquired. Internal procedures have been set up to ensure a full protection from virus
infection. Also software sent out on diskettes is checked against virus infection before it is sent off to theuser
P r o g r a m Distribution.
The request for computer codes has increased by about twenty percent during 1990 as compared to theprevious few years. In fact 1720 computer program packages (plus 130 additional reports) were sent out
to requesters 400 of these were sent to non-OECD establishments. This increase can be explained asfollows computer programs are increasingly used in a dual mode, small problems are solved locally ona personal computer while larger problems are executed remotely on a large mainframe. Data
communication is realized via a local or remote network connection. An increasing number of programs
exist now in both a PC and mainframe version. In 1990 about 350 PC versions of programs were
distributed (20%). This percentage has steadily increased over the last several years. Twelve percent of
the computer codes sent out in 1990 were not tested
Computer program abstracts were looked up by users in about 200 sessions and 25 requests were
deposited in the on-line program request mail box. In general an increasing number of requests isplaced via electronic mail

NUCLEAR DATA SERVICESC1NDA and EXFOR Activities
These activities are facing a temporary standstill following the departure of Simon Webster in August
1991. At programme to educate one of our supporting staff members in the tape-handling and loading of
CINDA and EXFOR data have been started. It is envisaged that a new physicist will be employed in thenear future
Concerning the CINDA activity, there is not much to report. The coverage of area 2 entries has
continued as usual
Three tapes of EXFOR data were produced and sent to other data centers in 1990. The tapes contained
30 new compilations and an additional 38 re-transmissions. There is no backlog for the EXFOR
compilation, but only some articles waiting to be compiled, as the numerical data has not yet been sent
to the Data Bank by the author.
NUMBER OF EXFOR ENTRIES COMPILED IN RECENT YEARSBY THE FOUR NEUTRON DATA CENTERS
WITH RESPECT TO THE YEAR OF REFERENCE
4-AUG.-1991
Subworks

Works

Year

75
76
77
78
79
80
81
82
83
84
85
86
87
88
89
90
91

Sum

700 421470 486487 506
564 1072
453 583
209 748
282 447404 818
253 482
207 551
232 703200 731
166 672
114 470
148 268
63 333
1
1

172
261
253
245
227
200
207
239
166
117
319
255
81
60
157
15
2

491
203
430
257
293
629
454
316
550
280
272
164
528
238
66
14
0

1784
1420
1676
2138
1556
1786
1390
1777

Sum

1451
1155
1526
1350
1447
882
639

98
84
82
86
70
49
60
69
47
54
47
41
36
26
28

425

15

4

1

70
82
60
93
68
66

23
35
39
37
39
37

65

32
37

57
36
51
43
31
20
40
36
33
1

31
24
34
30
17
14
25
4
1

48
47
63
16
26
39
14

17
69
25
38
38
47
20
8
4
0

239
248
244
232
203
191
' 171
180
183
154
162
140
120
100
97
56
3

Customer Service
254 requests for data and documents from 86 different requesters were "manually" answered in 1990.
This is a significant increase compared to the figure of 151 requests for 1989, but could be explained by
the fact that new versions of the three major evaluated data libraries (ENDF, JEF and JENDL) werereleased in 1990. The main items asked for were: JEF data (35%), other evaluated data (26%) and
EXFOR data (20%). Almost 30 percent of these requests came to the Data Bank via computer network.

Annex 4.8(cont. )A continued increase in the use of computer networks could be seen in the on-line customer service.
More than 1100 accesses to the data bases containing nuclear data were registered. The trends for thedifferent services are given in the table below showing the statistics since the introduction of the on-line
service in 1989.
NEADB ON-LINE STATISTICS

EXFOR
CINDA
EVALUATED DATA
ENSDF
NSR
NUDAT

1989

1990

1991 (JAN.-SEPT.)

98
14
64
309
358
66

132
29
155
314
424
79

64
30
128
114
240
77

Joint Evaluated File (JEF)
At the JEF Scientific Coordination Group Meeting on 1st June 1990, it was decided to abolish therestriction on the distribution of the JEF-1 evaluated library. The files were then released to users
outside the NEA Data Bank community. The decision affected also the group cross section libraries
derived from JEF-1. At the subsequent meeting in June 1991 it was decided to continue the present
policy for the distribution of the JEF-2 library, e.g. the JEF-2 library would be released world-wide after
the library had been properly benchmark tested. The benchmark testing programme was estimated to
run until about the end of 1992. The preliminary versions of the JEF-2 files would continue to bereleased within the framework of the OECD International Evaluation Project.
A preliminary version of the JEF-2 general purpose files (JEF-2.0) had, at the end of February 1990,
been sent out to laboratories involved in the benchmark testing of the library. Foreseen revisions tosome of the major isotopes was performed in the spring of 1990 and the revised data (JEF-2.1) were
issued in October 1990. Following feedback from the first use and benchmark testing of the JEF-2.1
data, a number of corrections to the existing files were discussed at the JEF meetings in December
1990 and June 1991 and it was decided to release an updated version called JEF-2.2 in September
1991.
The first versions of the JEF-2 Radioactive Decay Data and the Fission Yield Data were distributed fortesting in the middle of June 1990. A final version of the Fission Yield data were compiled at the end of
1990, whereas the work on the about 2300 isotopes present in the Radioactive Decay Data library will
not be terminated until the end of 1991.
The benchmark testing of the first version of the JEF-2 library has been started at several laboratories
directly involved in the JEF project.
Considering the amount of feedback from and the number of laboratories using the NJOY code, it was
felt of utmost importance to organise this feedback and the experience in the use of the code. It was
decided to create a "NJOY User Group" with E. Sarton as coordinator. One person from each major
laboratory involved in the processing of the JEF data were nominated to participate. The Group would
meet at regular intervals (4 to 6 months interval) and report back to the JEF Working Groups and the
JEF Scientific Coordination Group. The NJOY User Group would discuss experience in the use of thecode, suggest solutions to encountered problems, be the focal point for feedback, and be the central

body ior discussions with the authors of the NJOY code.
The first meeting of the NJOY User Group was held at the NEA Data Bank on 20th September 1991.
One of the objectives at the first meeting would be to assist in the organisation of a NJOY workshop, tobe held at the NEA Data Bank, tentatively on 7th and 8th May 1992.
The present cooperation between the JEF and EFF (European Fusion File) projects has been discussed
during 1990 and it has been agreed to ultimately merge the two libraries to a common library to be usedboth for fission and fusion purposes. A starter file of this common library, for which the acronym J/EFF is
proposed, will be prepared in 1992 from an agreed choice of isotopes from both libraries The two
projects would still keep their identities and work in parallel and close cooperation on the improvement of
the data

NUCLEAR SCIENCE ACTIVITIESThe NEA Steenng Committee had in 1990 asked for a simplification of the present structure of the NEA
Science programme K. Uematsu, the Director General of NEA, consulted widely within the nuclear
science community and presented a first proposal to the Steenng Committee meeting in April 1991. It
was suggested to merge the present NEA science committees, NEANDC and NEACRP, and the NEA
Data Bank Committee into one Committee, called the NEA Nuclear Science Committee. The Data Bank
scientific services would be overlooked by an executive group within the Nuclear Science Committee.
The Steering Committee generally supported the proposal to set up a Nuclear Science Committee, andinstructed the NEA Secretariat to draw up the required Terms of Reference. The NEACRP, NEANDC
and the Data Bank Committee were consulted when drafting the new Terms of Reference. At theSteering Committee meeting on 1st and 2nd October 1991 it was decided to establish a Nuclear
Science Committee to replace to old committees (NEANDC, NEACRP and the Data Bank Committee)
and the first meeting of the new committee was proposed for the 18th and 19th December 1991.

The International Evaluation Cooperation
The 3rd Working Group Meeting of the OECD wide International Evaluation Cooperation (IEC) was heldat ECN, Petten, Holland, in May 1991. The meeting reviewed progress in the work of the different
subgroups. Following a discussion on subject areas of interest to the evaluation projects, it was decided
to create four new subgroups•

Subgroup 8: Minor Actinide Data (Monitor: M. Sowerby)•

Subgroup 9: High Priority Request List for Data Needs in Future/Advanced Reactors. (Monitor andCoordinator: M. Salvatores)
Subgroup 10: Fission Product Inelastic Scattering. (Monitor H. Gruppelaar)
Subgroup
Subgroi 11. Inter-Comparison of the Resonance Region of
Larson)Cr,

Fe, and

Ni (Monitor: D

Unofficial requests for the participation of non-OECD experts at Working Group meetings had been
received Following a discussion, it was decided to allow for observers to be present at Working Group
meetings. The following procedure was decided: A maximum of three observers (at least one from the
IAEA) would be allowed, nominated through the IAEA Nuclear Data Section, and subject to approval by
the Working Group chairman. Nomination for observers should be sent to the Working Group chairman
with a copy to the NEA Secretariat well in advance of a meeting.

Annex 4.8(cont.)

Validation of Computer Codes and Data
An international nuclear mode code comparison concerning the Hauser-Feshbach theory wascompleted in 1990 Ten participants submitted results and of the 22 sets of results, 12 were sufficiently
consistent with each other to be accepted as benchmark values. The results were presented at theInternational Conference on Nuclear Data and Technology in Julich, Germany. A parallel comparison
study of Weisskopf-Ewing calculations gave such discrepant results that no benchmark values could be
identified
A blind intercomparison of codes used in decay heat calculations, was performed at the Data Bank in
1989 and 1990. The result of the exercise confirmed the hypothesis that the differences observed indecay heat calculations are due to the input data used and not to the calculational methods used in the
different computer codes. The conclusions were also presented at the Julich Conference.
A blind intercomparison of nuclear model cross section calculations of the Co-60 (n,p) reaction wasstarted in 1990. The first contributions from the participants were received at the end of 1990 and theanalysis of the results wilt continue in 1991.

IN-HOUSE COMPUTER INSTALLATION
The in-house computer installation has not recently been modified. The VAX computers performed ingeneral well with one exception: the VAX-11/780 suffered from some hardware problems and above all
slow performance mainly due to the increased load from on-line users. A proposal for a update of theinstallation has been discussed and it is foreseen to replace the present installation with a VAX 6510
computer and increase the number of Workstations (presently two VAXstation 3100).

Annex 4.9

NATIONAL NUCLEAR DATA CENTER
Status Reportto theEleventh Consultants' Meetingof the Nuclear Reaction Data Centers
7 - 11 October 1991

GeneralSince the last meeting of the Nuclear Reaction Data Centers in October 1989, our staff has been
decreased by one scientific and three support positions (there are currently 11
scientific/professional and 6 support staff). In addition, we have had two visiting scientists.
Vladimir Varlamov (CDFE) was at NNDC for five months doing photonuclear data compilation,
and working on future cooperation between the U.S.A. and the U.S.S.R. for the evaluation ofphotonuclear data. Wolfgang Rothenstein (from Haifa, Israel) is at the Center on sabbatical,
working on data and methods testing for thermal reactor applications.

Computer Facilities
In the past two years the following hardware has been added. All are networked into the VAX
cluster.
A Sun SPARCstation work station 1+ with 8mm tape, and two disk drives.
X-window terminals: 4 Dec-1200, 1 Dec-1000.
Four IBM-compatible PC's.
A diagram of the system as of September, 1991, is attached.

Bibliographies
The NSR activity has continued. 6 supplements of Recent References have been published. The
last edition of Charged Particle Nuclear Data Bibliography was published covering the literaturefrom November, 1988 through November, 1989.
As of sping 1990, the CINDA compilation activity has been severly cut back to those references
associated with the experimental data compiled at the Center.

Data Libraries
In the period from October 1989 through September 1991, 11 neutron data transmission tapes(TRANS 1235-1245) and 1 photonuclear tape (TRANS L004) were sent containing new andcorrected entries.
Compilation of the data from the Rider Fission Product Yield data file has been completed andmost of the data has been entered into the EXFOR system.

Evaluated Nuclear Reaction Data
NNDC continues to coordinate the work of the Cross Section Evaluation Working Group. The
ENDF/B-VI library was released in 1990 with unrestricted distribution, and contains complete
evaluations for neutrons incident on approximately 100 materials, and partial evaluations offission-product cross sections and dosimetry reactions. The ENDF/B Library also contains
neutron and proton reaction data for 56¥c at energies up to 1000 MeV. A library of chargedparticle data for proton with energies up to 100 MeV on two materials and for 5 reactions
important for fusion applications, as well as fission product yields and decay data were released
in 1991. Corrections to the initial releases, ENDF/B-VI Revision 1, were also released in 1991.
Plans are underway for the Symposium on Nuclear Evaluation Methodology which will be held
at Brookhaven in September 1992.

Nuclear Structure Data
NNDC continues to publish the Nuclear Data Sheets. As of September, 1991, issues throughVolume 64, #1 have been sent to Academic Press.

Customer Services
Since October 1, 1989, use of the online data service has steadily increased. There are nearly
300 customer accounts which may have more than one user, and 111 single user accounts. There
have been around 1000 retrievals per month this year with several months in which the number
exceeded 2000.

Publications
Fast Neutron Cross Section Newsletter, Issue #14 was published; issue #15 is in preparation.
A new edition of Nuclear Wallet Cards was issued in July, 1990.
The DOE compilation of requests for nuclear data will be done at Oak Ridge and published by
NNDC.

National Nuclear Data Center
Computer System
LN03 +
16 MB Memory

128 MB Memory

VAX 11/780

VAX 8820

Laser
MODEM

MODEM

I I

fin

I 1J I J !

MassbusUnlbustz

16 Async
Ports

DMR-11lino
Printer

56 KB Link to
Networks

9 tk Magtape(1600/6250 bpi)
125 Ips

r

TK50

X
HSC50
OX-20

8mm
Tape

fiber Optic
RepeaterStar Coupler

SC

ConsoleInteractive
Graphics

Link toCentral Facility

uVAX II
ConsoleTape Cart
Storage Controller

R053
Disk

Massbus Converter

LN03R
Tope
Controller

TX03
Postscript
Loser

SAO

SA1

SA2

SA3

SYSD

5 Fixed Media RA81 Disk Drives 456 MB each

IBM PC/AT
I41IA0

MKA1 URA2

MRAJ

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Brookhaven National Laboratory
Upton, N.Y. 11973
September, 1990

8 Async Ports

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National Nuclear Data Center
Computer System
NEW WINC
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100 MBDISKXWINDOWTERMINALX
WINDOWTERMINAL

IBM PC3 8 6 23MHZAEGIS OEV

17ZMB

150 MB
DISK

1.4MB
3.S FLOPREPEATER

Brookhavtn National Laboratory
Upton, N.Y. 11973
Sapttmber, 1990

On-line; Access Statistics

Retrievals* NSR ENSDF NUDAT CINDA CSISRS ENDF MIRD PLOT
814
1621
142
536
129
2521
815
60
863
4263
5022
1492
285
187
8748
1303
459
3253
1841
522
11
850
1649
150
121
8406
5613
2204
12067
187
1623
1256
1019
53
39
612
4079
201
8708
809
2245
489
38
10
D January toJune 24
The ilumber of pieces of information in each retrieval depends on the complexity of the retrieval

Year
1986
1987
1988
1989
1990
991®

Runs
648
1275
2264
3374
5436
4575

PHYSCO

XRAY

9
65
113

8
112

O
O
3
ft

3
3
(6
X

Annex 4.10
IAEA Nuclear Data Section

Progress Report
Staff
NDS lost long-term experienced staff: Alex Lorenz, who was the Deputy Head of theSection and was responsible for nuclear structure data; Monica Seits, who was the author ofmany computer codes for Cinda, Exfor and other systems; and Koichi Okamoto, author of
the NDS handbook on Nuclear Activation Data and scientific secretary of many meetings ina variety of topics.
New staff recruited instead are Doug Muir from USA, as Deputy Head of the Section
and head of the computer unit; S. Ganesan from India as a nuclear data expert for reactor
calculations; and Ramon Arcilla from the Philippines as a programmer.
The EXFOR compiler Vicente Osorio changed to the Physics Section. After somevacancy of this post he will be replaced by Harm Wienke, who will join the Section in
November 1991.
A professional post which had been vacant for some time, was finally lost.
There is significant staff shortage now, primarily for programming, but also in someother areas. There were delays in the answering of requests, in the processing of incoming
data libraries or codes, and in the preparation of reports and documents.

CINDA
After the publication of the big Archival Issue of CINDA, the photo-typesetting machine
was removed. The book production programmes had to be revised for a new laser printer.
Due to temporary vacancy of the programmers post, this re-programming could be done only
such that the 1991 issue of CINDA got published with a delay of half a year. The book is
now in print and will be distributed in November 1991.

EXFOR
The EXFOR coverage for area 3 was quite complete until early 1991, and a goodamount of backlog could be compiled. Due to the vacancy of the EXFOR compiler's post,
nothing has been compiled in the past six months, and no TRANS tapes were sent out in thisperiod.
V. Osorio produced a PC code for EXFOR compilation called ANDEX, which will now
be used in the Section. It is documented in IAEA-NDS-101.

-2-

The EXFOR system remained fairly stable. Changes and additions to Manual and
Dictionaries were mainly required for Photonuclear Data.
We have a backlog in EXFOR programming. In particular, the EXFOR check program
was not updated with the conclusions reached at the past NRDC Meetings. Consequently,
the check program now produces a lot of wrong error messages. We were not able to send
an updated check program to the other centers who had requested that.

Evaluated Data
The reporting period was characterized by a particularly large amount of new evaluateddata files. Significant efforts were required to make these files available to customers.
Several documents in the IAEA-NDS-series were produced, including IAEA-NDS-107 givinga joint index to these libraries.
It is still an important task for the customers services to work out the differences andpossible discrepancies between these libraries, and to advise customers which data may be
best for a given application.
NDS produced the following libraries:- "IRDF-90" (dosimetry) documented in IAEA-NDS-141;- a tape with selected data for geophysics applications "INGDB-90" documented in
IAEA-NDS-127;- FENDL (fusion applications); this is still being worked on;- activation libraries, mainly also for fusion applications:"ACTV-FUS/ECN" (from Petten) documented in IAEA-NDS-126;"ACTV-FUS/INT" documented in IAEA-NDS-148

Publications
The routine publications continued including-

INDC reports
Nuclear Data Newsletter
IAEA-NDS-documents
CINDA

Special publications were
- Nuclear Data for Safeguards (preliminary issue, being distributed in October 1991)- various meeting proceedings- translations of Russian reports

-3-

Annex 4.10
(cont.)

Computer
The main event will be the transition from the IBM mainframe to a VAX computer.
The consequences will be discussed during this meeting.

Request statistics
The request statistics for 1989-1991 is attached. Whereas the total number of requests
decreased slightly, there was a strong increase in the requests for evaluated data. In 1991
424 diskettes and 446 tapes were sent out.

Meetings
The NDS meeting calendar for 1991 to 1994 is attached, partly tentative.

NDS Request Statistics

1989
Area
Frequency

Biblio
Data

Codes

Doc's

E

Eval
Data

Expt
Data

Total

U

0

0

0

0

0

0

0

1

1

4

65

0

4

0

74

2

2

11

159

0

17

9

198

3

6

42

330

0

62

18

458

4

1

5

15

0

17

5

43

Total

10

62

569

0

100

32

773

1990
Area
Frequency

Biblio
Data

Codes

Doc's

E

Eval
Data

Expt
Data

Total

U

0

0

1

0

0

0

1

1

0

0

36

0

7

0

43

2

1

0

96

0

22

7

126

3

5

25

359

1

149

24

563

4

0

3

19

1

15

1

39

Total

6

28

511

2

193

32

772

1991
Area
Frequency

Biblio
Data

Codes

Doc's

E

Eval
Data

Expt
Data

Total

B

0

0

0

0

0

0

0

U

0

0

0

0

1

0

1

1

0

1

29

0

12

0

" 42

2

0

0

83

0

34

3

120

3

0

15

270

0

166

19

470

4

0

0

25

0

26

4

55

Total

0

16

407

0

239

26

688

rage No.
91.02.11
NUCLEAR AND ATOMIC DATA MEETINGS POR 1991
PROJECT TASK TYPE

DA1F.

LOCATIONTITLE

NDS STAFF

CODE

COST

GiC>4

1

FtCM

8 Jan-11 J a n ,1991

Brussels^ Belgium

Nuclear Data Needed for Neutron
Therapy (3rd RCM)

Kocherov

F4-RC-3AS.3

20800

G104

2

RCM

14 J«n-17 Jan, 1991

Bruisels. Belgium

Atomic and Molecular Data tor
Radiotherapy (2nd RCM)

Kocherov

F4-RC-405.2

31900

G103

11

RCM

13 May-17 May, 1991

Vienna, Austria

A+M Data for
Plasma-Interaction-Induced Ero«lon o*
Fusion Reactor Materials (l«t RCM)

Janev

F4-RC-47O

22400

16

CM

Jun-S Jun, 1991

Vienna, Austria

He-beam Data Base tor Alpha Particle
Diagnostics ot Fusion Plasma*

Janev

G101

18

1TC

3 Jun-22 Jun, 1991

Leningrad, USSRInterregional Training Course on
Targets and Samples *or Nuclear
Applications

Kocherov /
Wang

G103

10

CM

10 Jun-12 Jun, 1991

Vienna, Austria

Atomic Data Base for Be and B

Janev

4

RCM

17 Jun-19 Jun, 1991

Vienna, Austria

Compilation and Evaluation of Fission
Yield Nuclear Data (1st RCM)

Lammerjif —VJ~-

isooo

G101

13

AGM

23 Sep-24 Sep, 1991

Vienna, Austria

10th Meeting ot the A+M Data Centres
and ALADDIN Network

Janev /
Smith

F4-AB-781

12000

G104

iri

CM

2 J Spp-21!; Sep, 1991

Vienna, Austria

Nuclear Data Needs for Tight-lattice
Fission Reactors

Ganesan

(310~

12

AGM

25 Scp-27 Sep. 1991

Vienna, Austria

A+M Data for Fusion Plasma

Janev

Gldl

11

CM

7 Oct-11 Oct. 1991

Mo-.cow/ObninsI; USSR

11th Nuclear Reaction Data Centers
Meeting

GUI"

5

RCM

11 Nov-12 Nov. 1991

G10~

4

CM

13 Nov-15 J>Jov, 1991

GIOT-

2

AGM

IB Nov-22 Nov, 1991

9

AGM

Vienna. Austria

Vienna, Austria

Wang
Activation Cross Sections for the
Generation o-f Long-lived Radionucl Ides
(1st RCM)

F4-AG-717.2

12000
7000,

F4-RC-4A9

Methods o-f Calculation of Fast Neutron Muir
Nuclear Data for Structural Materials(replacing 4th RCM)

10900,7000

FENDL-2 and Associated Benchmark
Calculations

Muir /
F4-AS-759
Pashchenko

12000
12000

Nuclear Data Requirements for Fission
Reactor Decommissioning

Kocherov

to hr decidpd

Algeria

African Regional Workshop of XRF
Laboratory Network

Wang

F4-AB-782

-p•,

O

(cont

Vienna, Austria

or Morocco)

I
7000*

Lemmel2 Dec-A Dec. 1991

(or Sudan

7000

nne:

RllC

Vipnna, Austria

Impurities

7000

PROJECT TASK TYPE

14

DATE

STAFFS. CODE:V.-v-'

LOCATIONNDW

H> F e b - 1 3

Mar,

1992

ICTF

Trieste,

Italy

Glu"

f-CII

"1 M.xr -2 Apr, 197?

Chiang M,ii , Thailand

Oil i > 7

RfM

Hav

Vienna,Austria

yfc:' .i

Workshop on Computation and Analysis
o-f Nuclear Data Relevant to Nuclear
Energy and Sa-fety

Schmidt /Muir

Measurement and A n a l v ^ i ^ o-f 14 MeV
N e u t r o n - I n c l u c r d Doubl e—Di -f f ere-nti a l
Neutron Emission Cross S e c t i o n s Needed•for F i s s i o n and F u s i o n Reactor
Techno! ogy \ " r r i KCM)

Wang

F4-RC-376.3

12750

*)

Janev

F4-RC-470.2

25400

F4-AG-757.2

20000

A+M DataforF 1 asma— Interact 1 on— Induced Erosion o-f
Fusion Reactnr Materials <lnd RCM)
151'»I

13

AGM

17, Jun-16 Jun. 1992

Vienna, Austria

11th Meeting of the A+M Data Centers
and ALADDIN Networl

I3li>l

17

lit

irj

Otirun-Ll,

CIS

Interregional Training Course on
Nuclear Data and Measurement
Techniques in Nuclear Fvea^tor andPersona] Neutron Dosimetry

Fflslichenkn —b 1 <> 'H

RC<1

17 J u n - 1 9

Virnna.

Austria

Atomic and Molecular Data lor p)A^ma
Edge Studies iTnd F^CM)

janev

11

CH

1 Spp-3

Vienna,Austria

Technical A"sr>clct'= at irhn Nuclear
Reaction Data Centre Co-operation

Lemmel

(3102

9

AGM

Vienna,Austria

Nuclear Data Poqi.iirpmr>nr'i -for Fission
Reactor Decontrol ssi oni noi-.acherov

F4-AG-7Q2

20000

GJ'U

12

AGM

Meeting
Network

Lemmel

F4-AG-791

20000

Jun-lfi July.

199?

Jun. 1 9r

S e p . 1992

—11 Sc=p, 1 V 2
21 S p p - 2 5

Irtshl-pnt,

Sep. 1972

or

(910"

CM

1 CM

7 flct-9

Oct,

Geel ,CIS

1? Oct-16 Oct, 1992t h e NSDD E v a l u a t o r s "Pashchenko -Cadarache, Fr.-.nrt;

A+M and FMI Data -for Fusion Feactor
Technology

Janev

F4-TC-799

Cadarar.hp,

7th Meeting o-f the IFKC Sub-conimi tteron A+M Data -for Fusion

Janev

F4-TC-436.44

0F4-TC-440.38

15000

"I CM

1 16 O r t - 1 7

GI'ii

15

TCM

October/November 1992

Vienna, Austria

19th Meeting of the International
Nuclear Data Committee

Schmidt
successor

GH>"

2

Ct!

November 1992 (J days)

Vienna, Austria*) Integral Benchmark Testing of
FENDL-1

Pashchenko/ Ganesan

G103

15

RCM

November'''l992 (3 days)

Debrecen, Hungary*> Improvement o-f Neutron-induced He
Production Cross Sections (1st RCM)

Pashchenko

GI03

,.-,.

CM

. to^be_de(cidj?dFrance_ ^ Vienna, Austri^a'

'.0
03

16

199?

10000

Charged Parti elf and K-hot onucl ear
Cross Section Data -for Fusion

H101

Oct.

24000

Be?I giumB r o o l h a v e n , USA

1"92

o-f

F4-RC-443.2.:.,iU-... ..
.„ .
_ . .
Material Property Data or He Removal

15000

28 February 1992
NUCLEAR AND ATOMIC DATA MEETINGS FOR 1993

Project

Task

Type

Date

Location

Title

NDS staff

Code$ Cost

G.1.04

RCM

Jan./Feb.
1993

Vienna, Austria

Atomic and Molecular Data forRadiotherapy (3rd RCM)

Kocherov

F4-RC-405.3

44 950G.1.03

RCM

SpringSan Diego, USA

Activation cross sections for the

Pashchenko/

F4.10.08

20 0001993(in conjunction
with US Fusion

generation of long-lived radio-

Wang

F4.20.03

17 500(2 days)

nuclides (2nd RCM)

Nuclear Data
Meeting)G.1.02G.1.0312

G.I.01

RCM

Spring
1993

Vienna, Austria

Compilation and evaluation offission yield nuclear data (2ndRCM)

LammerSM

Jun 1993

Vienna. Austria

Plasma surface interaction
processes for tritium inventorycomputation

Janev

CM

Fall 1993

Vienna, Austria(adjacent toStandard input data sets fornuclear model computations of
nuclear data

Muir'ssuccessor

10 000Schmidt's
successor

20 000

15 00020th INDC Meeting)
G.1.02

1

AGM

Before20th INDC
Meeting

Vienna, Austria

Nuclear data requirements foradvanced thermal and fast reactors

G.1.01

18

TCM

Fall 1993

To be decided by

20th Meeting of the International

Schmidt's

INDC at 19th INDC

Nuclear Data Committee

successor

MeetingG.1.04SM

Sep. 1993

JAERI, Japan

Comparison of activation crosssection measurements andexperimental techniques

Pashchenko

O
O
3
rt
*

D
D
D
X
I—J

O

ID#5840N,p.3

28 February 1992
Nuclear and Atomic Data Meetings for 1993 - continued

Project

Task

G.1.03Type

Date

Location

Title

NDS staff

Code

AGM

Sep. 1993

JAERI, Japan

Review of uncertainty files
and improved multigroup crosssection files for FENDL-2

Ganesan/Pashchenko

20 00012th meeting of the A+M data
centres and ALADDIN network

Janev

20 000$ Cost

G.1.01

16

AGM

Sep. 1993

G.1.0114

AGM

Oct. 1993

Brookhaven, USA

13th nuclear reaction data centre
meeting

Lemmel20 000RCM

To be coordinatedwith Incineration
AGM

To be co-ordinatedwith Incineration
AGM

Neutron fission and capture crosssections of minor actinide isotopes(1st RCM)

Ganesan

18 000RCM

To be coordinatedTo be co-ordinatedwith Incineration
AGM

Nuclear data for neutron emissionin actinide fission (1st RCM)

Ganesan

18 000to be co-ordinatedNuclear data for design,operation and safety aspects ofnuclear waste incineration
faciIities

Ganesan

20 000G.1.04G.1.04

3

with Incineration
AGM
G.1.041

AGM

to be coordinatedwith NENF& NENP

with NENF & NENP

G.1.039

RCM

Atomic data for medium- and high-Z
impurities in fusion plasmas (3rd
RCM)

Janev

F4.30.05

20 000G.1.03

7

RCM

Plasma-interaction induced erosionof fusion reactor materials (3rd
RCM)

Janev

F4.30.04

20 000

ID#5840N,p.4

28 February 1992
NUCLEAR AND ATOMIC DATA MEETINGS FOR 1994

Project

Task

Type

Date

G.1.0117

NDW

Location

Title

NDS staff

Feb./Mar.

ICTP Trieste,

Workshop on nuclear data pro-

Schmidt's

1994

Italy

cessing and reactor physics

successor/

calculations for applications

GanesanCode$ Costin nuclear technology
G.1.02

CM

Mar. 1994

Vienna, Austria

Nuclear data for the estimationof potential radiation hazards
connected with reactor decommissioning

Kocherov

10 000

14 000G.1.03

6

RCM

May 1994

Bratislava, CSFR

Measurement, calculation andevaluation of photon production
cross sections

Kocherov

G.1.02

4

RCM

Fall 1994

Vienna, Austria

Compilation and evaluation offission yield nuclear data (3rdRCM)

Lammer

G.1.01

15

AGM

Fall 1994

Meeting of the NSDD evaluator's

Lemmel

F4.20.03

17 500

20 000

network
G.1.03

RCM

Sep. 1994(3 days)

Vienna, Austria

Improvement of neutron-induced

Pashchenko

F4.10.10

24 000

He production cross sections (2ndRCM)

G.1.03

G.1.03

ID#5840N,p.5

AGM

CM

Sep. 1994(5 days)

Vienna, Austria

Benchmark and sensitivity studies

Pashchenko/

for FENDL-2

GanesanSep. 1994(2 days)Arzamas, CIS

International library of charged

PashchenkoorLivermore, USAparticle fusion reaction crosssections

20 000

10 000

>
O 3
O 3
3 (T)
rt X

28 February 1992
Nuclear and Atomic Data Meetings for 1994 - continued

Project

Task

G.1.04Type

Date

Location

Title

NDS staff

RCM

Sep. 1994(3 days)Arzamas, CIS
orInternational reference datalibrary of nuclear activation
cross sections (1st RCM)

Pashchenko

Livermore, USA

Code$ Cost16 000G. 1.01

19

TCM

Sep. 1994

Vienna, Austria

8th Meeting of the IFRC Subcommittee on A+M Data for Fusion

Janev

G. 1.01

16

AGM

Sep. 1994

Vienna, Austria

13th Meeting of the A+M data
centres and ALADDIN network

Janev

20 000G. 1.01

14

CM

Oct. 1994

Vienna, Austria

Technical aspects of nuclear
reaction data processing andexchange

Lemmel10 000G.1.0121

ITC

Nov. 1994

Dresden, Germany

Interregional Training Course on
nuclear data measurements andapplied neutron physics researchwith neutron generators andassociated r a d i a t i o n protection
aspects

Kocherov

G.1.04

2

RCM

Vienna, Austria

Neutron fission and capture crosssections of minor actinide isotopes (2nd RCM)

Ganesan

18 000G.1.04

3

RCM

Vienna, Austria

Nuclear data for neutron emissionin actinide fission (2nd RCM)

Ganesan

18 000G.1.02

7

CM

Vienna, Austria

Representation and processing of
neutron cross sections in theunresolved resonance region

Ganesan

10 000G.1.0315

RCM

Radiative cooling rates of fusion
plasma impurities (1st RCM)

Janev

14 000

ID#5840N,p.6

28 February 1992
Nuclear and Atomic Data Meetings for 1994 - continued

Project

Task

Type

G.1.038

G.1.04

5

Date

Title

NDS staff

RCM

Reference data for thermal
response of fusion-plasma facing
materials exposed to high heatand particle fluxes (3rd RCM)

Janev

18

000

CM

Standard reference data library ofradioactive decay half lives

Lemmel

10000

LocationCode$ Cost

/—N

>

O 3
O 3
3 tr>
rr X

ID#5840N,p.7

Annex 5
Seminar on Intermediate Energy Nuclear Data
held during the 11th IAEA Consultants' Meetingof the Nuclear Reaction Data Centers
Obninsk, 9 October 1991
1.

Shubin, FEI Obninsk
Summary of theory and calculations in the field of Intermediate Energy data at the FEI
Obninsk.

2.

A.V. Daniel, RI St. Petersburg
Intermediate Energy Nuclear Data at the Radium Institute. See Annex 5.1.

3.

S. Pearlstein, NNDC, Brookhaven
Activities at the NNDC in the field of Intermediate Energy Nuclear Data.

4.

V. Pronjaev, CJD Obninsk
Nuclear structure effects by different reaction mechanisms in the cross-section andspectra in the intermediate energy range.

5.

V.A. Vokolov, CAJaD Moscow
Some problems of the cross-section evaluation for charged-particle monitor reactions.

Annex 5.1

INTERMEDIATE ENERGY NUCLEAR DATAAT THE RADIUM INSTITUTE
A. v. Daniel, V. Yu. Perov, V. A. Rubchenya
A. A. RlmsKl-KorsaKov
v. G. K n l o p m Radium Institute
St. Petersburg, USSR
( ABSTRACT }The importance of intermediate energy nuclear datafor contemporary technical applications is now widely accepted.
The Key issue in this field ( from our point of view ) is thecorrect Monte-Carlo calculation of space- and energy distributions of various particles in the target construction, irradiated by the primary beam. The "inclusive" and "exclusive" approaches are usually considered.
It has been shown [l] that m the "exclusive" approach using the nuclear models such as [2] and its modifications tends to underestimate the high-energy neutron yields, Thissituation will probably lead to revision of the models - but inthis field we at the KRI do not plan at present any serious effort, since tradltlonaly we are using the "inclusive" method.
Different approaches to approximation problem
The "inclusive" approach is based •: a solving a system
of Integral equations for radiation transport, where the integral operater A can be presented as a.superposition of transport
operator T and interaction operator K. The kernel of the latterincludes a function describing dovible-differential spectra ofsecondary particles in the particle-nucleus interaction. Thisfunction { for practical purposes ) can be an approximation of
the existing experimental or calculated data. The whole successof the "inclusive" method depends on the accuracy of the approximation used.
We have analysed a number of Known approximation systems such as Hassgen's [3], SychoV s [4], Pearlstem's [5,6] and NaKahara J s [7] - to find that ( naturally ) they are not universally applicable and in some cases even contradict one another.
For instance, Fig.l shows that the mean Kinetic energy carriedby outcomlng protons in the wide primary energy range ( from 50
to 1OOO MeV ) coincides nicely in Hassgen's n ] and sychov's [4]approximation. The same quantity for neutrons mtheir approximations differs significantly( see Fig. E ). The mean Kinetic
energies, carried by secondary protons and neutrons { and theirmultiplicities ), calculated by Pearlsteln's methods [5,6] exceed systematically the values, calculated by methods [3] and [4].
-More than that, in our evaluation by the [5,6] method the total
Kinetic energy of secondary particles for lead target nucleus may
exceed the energy of the primary proton. This can be caused byindependent way of approximating the proton and neutron spectra.
On the other hand, Pearlsteln's approximation gives the best aggreement with neutron spectra [l] for thin lead target bombarded
by 590 MeV protons { see Fig, 3 ), which should not be surprising,since this approximation was probably based on this experiment,
The TsuKada-NaKahara's approximation [7] overestimates the neutron yields compared to experiment [13, while Hassgen's [3] andSychov's [4] methods underestimate the same , especially forlarge angle values.
This comparison of approximation methods [3,4,5,6,7] haslead us to conclusion, that the existing systems for approximate
description of double-differential particle spectra should be
revised, and probably some better new approximation system should
be developed. In this case, such future approximation systems
must comply to a certain set of principles :- first, the complete information on experimental and caicuiatlonal data to build such system is needed ;- second, the system must permit a relatively simple parametercorrection procedure, and should permit further fitting ofsome independent parameters to correct the curves when new,more accurate data become available ;- third, the system must not contain internal contradictions,that is it must comply to some definite integral rules.
The first two principles are valid in Fearlstein's [5,6] andTsuKada-NaKahara [7] systems. The last principle holds best in the
Sychov's [4] case, which unfortunately practically does not comply
to the second principle. Tills second principle will be ( probably)
suited best in case of a system using a wide choice of parameters
fitted to separate nuclei and incident particles, and also using
one group of parameters for limited incident energy intervals. To
build such approximation system one will need extensive data on
double-differential particle spectra, 'and that means accumulation,
evaluation and exchange of a large volume of data.
Another systematics is being developed at KRI for fission
product yields for fission, induced by various means. The fractional independent yield after the emission of prompt fission neutrons is approximated by :Y^-CA, Z) = 2r* , Y^ (A+n) * Pt-» (A+n, Z) * W(n,A+n,Z)n*'where : Y t (A+n) is the mass distribution before prompt neutrons,
P* (A+n,Z) Is the lsobaric chain distribution before
prompt neutron emission,
W(n,A+n,Z) is probability of emission of n neutrons fromfragment (A,Z).
The primary mass distribution Y (A+n) war approximated by seven Gaussians, related to shell structure influence. The parameters of charge distribution P (A, Z) and multiplicity distribution
W(n,A+n,Z) dependence on E,A, Z of compound nucleus and on A and zof target nucleus is taken into account. The parameters of Y (A+N)
distribution were found from experimental data for spontaneous
fission and thermal neutron induced fission.
Medium energy library - plans and status
The structure of medium energy data bank, that we hope tocompile and use, has been planned. It involves fovir data levels
which differ in data character and also in the software support.
The first level relates to thin target experimental dataand perhaps calculations based on various nuclear models. The international exchange on such experimental data is done in EXFOR
format. Special re-formatting software will be necessary to con-

Annex 5.1(cont.)
vert this data to database form for evaluations.
The second level will store evaluated nuclear data m the
ENDF/B-VI format.
The third level is for systematics parameters, fitted tothe evaluated data of the second level.
The fourth level is for benchmark experimental data frommeasurements with large target assemblies, that will be necessary
for verification of integral modelling of medium energy radiationtransport, and for correction of the whole process.
At present we have partly implemented the structure andsoftware support of this project, namely :- with the help of IAEA NDS we started to use the E X F O R coding ofexperimental data - and the ANDEX package for PC, that was
brought here by V, Osorio is now used extensively.
- we developed a svipporting package to extract the EXFOR-coded
data into our mainframe EC-i045 computer in database format.
- the 1989 ENDF Pre-processing Codes IAEA-NDS-39 [9] are now usedon our mainframe for ENDF library data work, and our internal
neutron data library HECSF [10] has been composed for some calculations.
- as a main instrument for parameter evaluation we implemented
the CERN package MINUIT [11], and now have started work on theparticle spectra with integral restricting rules.
- the analysis of large target experiments is done by our "inclusive" model package SITHA [IH, 13], which takes into cosideratlon protons,neutrons and charged pions in tne energy range from20 KeV to 10 Gev, and only neutrons be l'<•'•• £0 Mev, in the lattercase we use an original multigroup cron-s-section library named
GR175-V1 [13].
We hope to continue this project wi+n the help of the established Nuclear Data Centers both in the USSR and abroad, and weare grateful for their constant support and understanding.
REFERENCES :1. S. Cierjacs et al. , Phys. Rev. C, 1987, v. 3->, p. 1975
2. K. Ishlbashl et al. , JAERI-M 90-025, 199O, p. 362
3. K. Hannsgen and J. Ranf t, comp. Phys. comm. 1986, v. 39, p. 53
4. B. S. Sychov et al. , Preprint RTI AN SSSR, No. 799, M. 1979
5. S. Peai^lstein, Nucl. Sci, Engng. 1987, v. 95, p. 116
6. S. Pearistem, Astrophys, J. 1989, v. 346, p. 1049
7. K. Tsukada and Y. Nakahara, Atomkernenergie-Kerntechnik,
1964, V. 44, p. 186.
6. D. E. cuiien, Program X4T0C4. , I A E A - N D S - 8 0 , 1985
9. D. E. Cullen, The 1989 ENDF Pre-processin Codes,
IAEA-NDS-39, 1991.
10. A.V.Daniel and G. V. Matveev, Neitronnaya Fisica,
M. CNI IAtominf orm, 1984, v. l, p. 53
11. F.Janes and M. Roos, MINUIT, CERN Program Library D506
12. A.V.Daniel Preprint Rl-181, M. , 1984
13. A.V.Daniel Preprint JINR P3-91-32O, Dubna, 1991

1 r

xxxxx Pearlstein
AAAA Hanssgen et al
w y Sychov et al500( MeV )

1000

Rg.1 Numbers of emitted protons one!
mean kinetic energies taken away
by protons in reaction Pb(p,p)X
when E?>/50 MeV.

Annex 5.1(cont.)

3rr

* i

m

4CG

UJ

0,
0

I 1 I I I I I I I I I I I I I 1 I I

500
MeV

1000

Fig.2 Numbers of emitted neutro's end
mean kinetic energies taken away
by neutrons in reaction Pb(p,n)X
when En ">/ 50 MeV. Oesignaticns
are the same as in FTg.1.

Pearlstein^
Cierjcck et al\
Hassgen et a!
Sychov et alaaa Tsukada et al

10 "s
10

~

10- 7

i

10

i

1

i i n mlii i i ) till

102

10

i

I

l l l l l l

10 3

E (MeV)

Fig.3 Double differential spectraof neutron emitted throughreaction Pb(p,n)X, Ep=G00 MeV.

Annex 6

Minutes of the INDC Subcommittee on Data Center Support
Reproduction from Appendix 12 of the INDC Meeting Minutes 1990

Members:

O. Bersillon
M.V. Blinov
M.S. Coates
F. Frohner
R.C. Haight
S.S. Kapoor

FranceUSSR
UK
Germany (Chairman)
USA
India

B.D. Kuzminov
H.D. Lemmel
Liu Tingjin
Y. Nakajima
R.W. Peelle
J J . Schmidt

USSR
IAEA/NDS
PR China
Japan
USA
IAEA/NDS

Immediate Goals
The SC was convened ad hoc to address the problem described by Lemmel in
INDC/P(90)-26 as follows: "Due to continuing budget reductions the staff situation at the
co-operating nuclear data centers has now reached a stage that the international data bases
CINDA/EXFOR, CPND-EXFOR, NSR/ENSDF, are gradually deteriorating. In future, data
users will no longer receive complete and updated information out of these data bases".
It was discussed what actions could be taken to- avoid further reduction of manpower in nuclear data centers;- resume recently interrupted data center activities (Germany, US, UK, others);- to start additional data activities in important areas (CPND, medium-E data, A chain
evaluation).
and to address, in particular, the immediate main problems,- lack of staff at NNDC for CINDA and EXFOR;- CPND compilation and evaluation;- need for additional A chain evaluators.
The SC expressed great concern, in view of the implications of a deficient nuclear database for nuclear activities of world-wide and growing urgency, viz.
-reactor safety,
nuclear waste management,
reactor decommissioning,
fusion research and development (NET, ITER).

The outcome of the discussion was that appeals via "diplomatic" and IAEA channels are
not likely to be enough.
The actions agreed upon are listed in Appendix 3. Actions 55 to 60.

Appendix 3

ACTIONSARISING

FROM

18TH

INDC

MEETING

No

SessionRespondents

Action

55.

DC SC

NDS

Prepare by the end of October 1990 a
concise "awareness document", with aclear warning what cannot be expectedby nuclear data users any more if
nothing is done, directed at decision
makers who are not necessarily
physicists, with a few pertinent chartsand figures. This should be mailed to
INDC members.

56.

DC SC

INDC members

Use of the "awareness document" in homecountries to enhance awareness among
affected groups (in universities,
national labs, industry, others) andespecially among policy makers.

57.

DC SC

INDC members

Explore potential useful addresses ofletters to be written by IAEA (both DDG
and NDS level), provide NDS with theaddresses by end of 1990.

58.

DC SC

Head, NDS

See to it that these letters are sentout to the addressees proposed by themembers.

59.

DC SC

INDC Chairman

Send letter to NEANDC and NEACRP
chairmen to inform them and ask them toparticipate in a concerted effort.

60.

DC SC

NDS

Make sure that the data center
emergency is brought to the attentionof the participants of the 1991 Julichconference, e.g. in the papers on thedata centers and on ENSDF.

ANNEX 7

Working papers on Exfor Trans tapes

Disturbing mistakes in Exfor TRANS tapes

O-Schwerer

This is a summary of more important mistakes in Exfor transmission tapes
as found by NDS.

- Isomeric ratios should be given as implicit ratios -M/G, -M/T, etc.,
not as explicit cross section ratios- Use of heading DATA-ERR where more specific headings are available(ERR-T, ERR-S etc.)- E-format data not right-adjusted within field- Incorrect use of PAR in REACTION SF 5
(e.g. with SPC in SF 6 or EL in SF 3)- Confusion of units PER-CENT, NO-DIM and ARB-UNITS- SPA missing in SF 8 for reactor spectrum- redundant particle considered- missing or inconsistent HISTORY entries- REACTION code and units not consistent- use of FLAG for distinguishing different reactions(instead of using different REACTION codes)- missing incident particle energy- particle codes in SF 3 must be given in increasing ZA order(except when SEQ is given in SF 5)

Pending EXFOR retransmissions

O.Schwerer

Please find attached a reminder as for which EXFOR entries are still pending
for retransmission as requested by NNDC and NDS from NNDC, NEA-DB, NDS, CJD and
CAJaD.
When mistakes are found in TRANS tapes, retransmission is requested for thosecases where the correction to be done is not obvious. According to our records,
requests for retransmission remained without response for the EXFOR entries
listed. May we ask each center to review this list, update the listed entries
and retransmit them.

2 3 APR 92

SEARCH EXFOR XREF FILETRANS

ACCESSION #A017

A0229004

A017

A0317004

A017

A0329002

A018

A0320002

A019

A0178001

A019

A0198001

A019

A0202002

A019

A0202003

A019

A0202004

A019

A0345003

A019

A0345010

A020

A0319023

A020

A0319030

A020

A0322005

A020

A0347004

A020

A0352004

A020

A0363001

A020

A0364001

A020

A0365001

RE-TRANSMITTEDPAGESEARCH EXFOR XREF FILE

23 APR 92
TRANS

ACCESSION #A021

A0366001

A021

A0371001

A021

A0387007

A021

A0388001

A02L

A0393002

A021

A0393004

A022

A0399001

A024

A0294001

A025

A024

A0431002

A025

A024

A0431003

A025

A024

A0434002

A025

A024

A0434003

A025

A024

A0434004

A025

A024

A0471002

A025

A024

A0476002

A025

A024

A0476003

A025

A024

A0476004

A025

RE-TRANSMITTED

Annex 7
(cont.)PAGE
2

SEARCH EXFOR XREF FILE

23 APR 92
TRANS

ACCESSION #RE-TRANSMlTTED

1072

11532006

1077

11863002

1077

11863003

1085

12435002

1085

12435003

1101

12627002

1119

11281010

1136

12355002

1136

12355006

1136

12355007

1159

10391081

1215

10574002

1246
1246

1216

10800002

1245

1216

10800003

1245

1217

10142002

1229

13119002

1230

12991002

1230

12991003

1232

11010001

1232

13132001

1232

13156001

1233

13066003

1233

13066004

1233

13073002

1233

13092002

1233

13092003

1242

13195002

1242

13195003

PAGE

SEARCH EXFOR XREF FILE

23 APR 92
TRANS

ACCESSION #2081

20775003

2083

20876018

2083

20876021

2089

20742005

2091

21793?03

2100

21904002

2100

21904003

2100

21904004

2100

21904005

2100

21914003

2101

21910004

2101

21910005

2101

21910006

2101

21910009

2101

21910010

2101

21910011

2102

21944002

2103

21883004

2103

21883005

2103

21883006

2103

21883007

2103

21883008

2103

21883010

2110

21993002

2110

22000001

2110

22001021

2110

22001022

2110

22003002

RE-TRANSMITTED

Annex 7 (cont.)
PAGE
1

23 APR 92

SEARCH EXFOR XREF FILETRANS

ACCESSION #2117

22027005

2117

22031151

2117

22031152

2117

22031153

2117

22031154

2117

22031155

2117

22031156

2117

22031157

2117

22031158

2117

22031159

2118

22050001

2118

22039002

2122

22032002

2122

22032003

2122

22052004

2122

22057003

2128

22156015

2128

22157055

2128

22157057

2128

22157073

2128

22157087

2129

21928001

2129

22116002

2129

22116003

2129

22116004

2129

22129001

2129

22130001

2129

22143002

2129

22143003

2129

22161002

RE-TRANSMITTEDPAGESEARCH EXFOR XREF FILE

23 APR 92
TRANS

ACCESSION #

3061

30755010

3062

30739004

3064

30808005

3069

30817001

3071

30390001

3071

30394013

3071

30640001

3071

30640002

3071

30710003

3071

30932003

3072

30264041

3077

30139001

3078

30016002

3078

30218002

RE-TRANSMITTED

Annex 7 (cont.)
PAGE
1

SEARCH EXFOR XREF FILE

23 APR 92
TRANS

ACCESSION #4034

40181002

4034

40181003

4034

40264004

4034

40348003

4043

40420021

4043

40420041

4043

40580002

4052

40651003

4053

40577001

4055

40788001

4055

40792001

4055

40793001

4056

40576003

4057

40731004

4057

40749002

4058

40839002

4058

40839003

4058

40839004

4058

40839005

4058

40839006

4060

40528009

4060

40611003

4060

40611004

4060

40611005

4060

40611006

4060

40869002

4066

40915003

4066

40916002

RE-TRANSMITTED

PAGE

23 APR 92

SEARCH EXFOR XREF FILETRANS

ACCESSION #4069

40930001

4073

40636001

4075

40965001

4075

40974003

4081

40996002

4082

40541001

4083

41038001

RE-TRANSMITTED

Annex 7 (cont.)
PAGE
2Annex 8
GLOSSARY OF ABBREVIATIONSBNLBrookhaven National Laboratory, Upton, N.Y., USA

BROND-2

Russian evaluated neutron reaction data library

CAJaD

Center for Nuclear Structure and Reaction Data, Kurchatov Institute, Moscow,
RussiaCDFE

Centr Dannykh Fotojad. Eksp., Moscow State University, Russia

CENDL-2

Chinese evaluated neutron reaction data library

CINDA

A specialized bibliography and data index on neutron nuclear data operated
jointly by NNDC, NEA-DB, NDS and CJD

CJD

USSR Nuclear Data Center at F.E.I., Obninsk, Russia

CNDC

Chinese Nuclear Data Center, Beijing, P.R. China

CP...

Numbering code for memos exchanged among the NRDC

CPNDCharged-particle nuclear reaction data

CRP

Coordinated Research Programme of the IAEA Nuclear Data Section

CSEWG

US Cross-Section Evaluation Working GroupCSISRS

Cross-Section Information Storage and Retrieval System, the EXFORcompatible internal system of NNDC

EFF

European evaluated nuclear data file for fusion applications

ENDF-6

International format for evaluated data exchange, version 6

ENDF/B-6 US Evaluated Nuclear Data File, version 6
ENSDF

Evaluated Nuclear Structure Data File

EXFOR

Format for the international exchange of nuclear reaction data

FEI

Fiziko-Energeticheskij Institut, Obninsk, Russia

FENDL

Evaluated nuclear data file for fusion applications, developed by IAEA-NDS

IAEA

International Atomic Energy Agency

IFRC

Intenational Fusion Research Council

INDC

International Nuclear Data Committee

INIS

International Nuclear Information System, a bibliographic system

IRDF

The International Reactor Dosimetry File, maintained by the IAEA'-NDS

ITER

International Thermonuclear Experimental Reactor

JAERI

Japan Atomic Energy Research Institute

JEF

The Joint Evaluated File of neutron data, a collaboration of European NEA
member countries and Japan

-2-

LEXFOR

Part of the EXFOR manual containing physics information for compilers

NDS

IAEA Nuclear Data Section, Vienna, Austria

NEA

Nuclear Energy Agency of the OECD, Paris, France

NEA-DBNEA Data Bank, Saclay, France

NND

Neutron Nuclear Data

NNDC

National Nuclear Data Center, Brookhaven National Laboratory, USA

NNDEN

Neutron Nuclear Data Evaluation Newsletter

NRDC

the Nuclear Reaction Data Centers

NSDD

Nuclear structure and decay data

NSR

Nuclear structure references, a bibliographic system

OECD

Organization for Economic Cooperation and Development, Paris, France

PC

Personal Computer

PhND

Photonuclear data

RI

Radievyj Institut, Sankt Peterburg, Russia

RIKEN

Nuclear Data Group, RIKEN Inst. of Phys. and Chem. Res., Wako-Shi,
Saitama, Japan

SG,SGIPStudy Group for Information Processing, Sapporo, Japan

TRANS

Name of transmission tapes for data exchange in the EXFOR system

WRENDA

World Request List for Nuclear Data

4C...

Numbering code of memos exchanged among the four Neutron Data Centers