International Atomic Energy Agency

INDC(NDS)-308
Distr. G,NC

I N

DC

INTERNATIONAL NUCLEAR DATA COMMITTEE

Co-ordination of the Nuclear Reaction Data Centers
Report on an IAEA Advisory Group Meeting
hosted by the NEA Data Bank
Paris, 25-27 April 1994

Edited by
O. Schwerer, C.L. Dunford, H.D. Lemmel
July 1994

IAEA NUCLEAR DATA SECTION, WAGRAMERSTRASSE 5, A-1400 VIENNAINDC(NDS)-308
Distr. G,NC

Co-ordination of the Nuclear Reaction Data Centers
Report on an IAEA Advisory Group Meeting
hosted by the Nea Data Bank
Paris, 25-27 April 1994

Abstract: This report summarizes the 1994 co-ordination meeting in Paris, France, of thenational 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 anddata center services,
the exchange and documentation of evaluated 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. The scope of data
covers microscopic cross-sections and related parameters of nuclear reactions induced byneutrons, charged-particles and photons.

Printed by the IAEA in Austria
September 1994

CONTENTS

List of Acronyms

1

The network of Nuclear Reaction Data Centers

3

Past NRDC Meetings

5

Summary Report

6Center Heads Discussions

11

Draft:

Coordination of Activities within theInternational Nuclear Data Community

12

Technical Discussions

13

Appendices

15

1.
2.
3.
4.
5.
6.
7.
8.
9.

List of participants
AgendaConclusions and Actions resulting from the Technical Sessions
E-Mail Addresses
Media for data exchange between Centers
Draft proposal: CRP on Photonuclear Data
Data evaluation activities of the CPND centers
Progress reports
Working Papers

-1 LIST OF ACRONYMS
ATOMKI

Nuclear Research Institute, Debrecen, Hungary

BNL

Brookhaven National Laboratory, Upton, N.Y., USA

BROND-2

Russian evaluated neutron reaction data library, version 2

CAJaD

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

CDFE

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

CENDL-2

Chinese evaluated neutron reaction data library, version 2

CENPLChinese evaluated nuclear parameter library

CINDA

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

CJD

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

CNDC

Chinese Nuclear Data Center, Beijing, 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 EXFOR-compatible 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

International 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

-2-

JCPRG

Japan Charged-Particle Nuclear Reaction Data Group, Sapporo, Japan(previously Study Group for Information Processing)

JEF

The Joint Evaluated File of neutron data, a collaboration of European NEA
member countries and JapanJENDL-3

Japanese Evaluated Nuclear Data Library, version 3

LEXFOR

Part of the EXFOR manual containing physics information for compilers

NDS

IAEA Nuclear Data Section, Vienna, Austria

NDS

The journal Nuclear Data Sheets

NEA

Nuclear Energy Agency of the OECD, Paris, France

NEA-DBNEA Data Bank, Paris, France

NEANDCNEA Nuclear Data Committee

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

NRDF

Japanese Nuclear Reaction Data File

NSDD

Nuclear structure and decay data

NSC

Nuclear Science Committee of the NEA

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

TRANS

Name of transmission tapes for data exchange in the EXFOR system

USDOE

U.S. Department of Energy

WRENDA

World Request List for Nuclear Data

4C..

Numbering code of memos exchanged among the four Neutron Data Centers

-3-

The Network of Nuclear Reaction 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
CNDC
ATOMKI
RIKEN
JCPRG
JAERI
(KACHAPAG)

1.

US National Nuclear Data Center, Brookhaven, USA
OECD/NEA Nuclear Data Bank, Saclay, France
IAEA Nuclear Data Section
Centr po Jadernym Dannym (= Nuclear Data Centre),
Obninsk, Russia
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
Chinese Nuclear Data Centre, Beijing, P.R. of China
Nuclear Data Group of the ATOMKI Institute, Debrecen,
Hungary
Nuclear Data Group, RIKEN Institute of Physical and Chemical
Research, Wako-Shi, Japan
Japan Charged-Particle Nuclear Reaction Data Group, Sapporo,
Japan
Nuclear Data Center of the Japan Atomic Energy ResearchInstitute, Tokai-Mura, Japan(Karlsruhe Charged Particle Group, Karlsruhe, Germany.
Discontinued in 1982, its responsibilities were taken over by
CAJaD)

Neutron Nuclear Data
La

Bibliography and Data Index CINDA:
Input prepared by NNDC, NEA-DB, NDS, CJD, CNDC, JAERI
Handbooks published by IAEA
Online services by NNDC, NEA-DB and NDS

l.b

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

l.c

Data Handbooks based on EXFOR
published by NNDC (last issue in 1984)

-4l.dEvaluated data exchanged in ENDF format:
NNDC, NEA-DB, NDS, CJD, CNDC, JAERI and others.
libraries:
BROND-2 (Russia)
CENDL-2 (China)
ENDF/B-6 (USA)Main data

IRDF-90, Rev. 92(IAEA)
JEF-2 (NEA)
JENDL-3 (Japan)

Online services by NNDC, NEA-DB and NDS

2.

3.

l.e

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

l.f

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

Charged Particle Nuclear Data (including heavy-ion reaction data)
2.aBibliography NSR published by NNDC
Online services by NNDC, NEA-DB and NDS

2.b

Numerical data exchanged in EXFOR format:
Input prepared by CAJaD, RIKEN, CNDC, ATOMKI (from 1992), NDS,
NNDC, JCPRG
Online services by NNDC, NEA-DB and NDS
Coordination of compilation: CAJaD

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

2.e

Evaluated data in ENDF format:
NNDC, NDS, CAJaD, ATOMKI

Photonuclear Data
3.a

Numerical data exchanged in EXFOR format:
Input prepared by CDFE, occasional contributions from NNDC, NDS
Online services by NNDC, NEA-DB and NDS

3.b

Bibiliography published by CDFE and JAERI

3.c

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

-5-

Past NRDC Meetings
Paris, 25-27 April 1994

Center Heads + Tech.
= 12th NRDC Meeting

Vienna, 1-3 Sept 1992

Technical

INDC(NDS)-279

Obninsk, 7-11 Oct 1991

Center Heads + Tech.
= 11th NRDC Meeting

INDC(NDS)-262

Vienna, 13-15 Nov 1990

Technical

Memo CP-D/210

Vienna, 2-4 Oct 1989

Center Heads + Tech.
= 10th NRDC Meeting

Memo CP-D/200

Vienna, 4-6 Oct 1988

Technical

Memo CP-D/190

Brookhaven, 27-29 Oct 1987

Center Heads + Tech.
= 9th NRDC Meeting

INDC(NDS)-204

Vienna, 7-9 Oct 1986

Technical

Memo CP-D/159

Saclay, 9-11 Oct 1985

Center Heads + Tech.
= 8th NRDC Meeting

INDC(NDS)-178

Vienna, 19-21 Sept 1984

Technical

MemoCP-D/131

Obninsk + Moscow,
17-21 Oct 1983

7th NRDC Meeting

INDC(NDS)-154

Vienna, 3-7 May 1982

6th NRDC Meeting

INDC(NDS)-141

Brookhaven, 29.9 - 2.10.1980

5th NRDC Meeting

INDC(NDS)-125

Karlsruhe, 8-13 Oct 1979

4th NRDC Meeting

INDC(NDS)-110

Paris, 19-23 June 1978

3rd NRDC Meeting

NEA-NRDC-3= INDC(NDS)-99

Kiev, 11-16 April 1977

2nd NRDC Meeting= 3rd CPND + 13th 4-C

INDC(NDS)-90

Vienna, 28-30 April 1976

2nd CPND Meeting

INDC(NDS)-77

Vienna, 26-27 April 1976

12th 4C-Meeting

INDC(NDS)-78

Vienna, 8-12 Sept 1975

CPND Meeting

INDC(NDS)-69+71

Brookhaven, 10-14 March 1975

11th 4C-Meeting

INDC(NDS)-68

Paris, 6-10 May 1974

10th 4C Meeting

INDC(NDS)-58

Vienna, 24-26 April 1974

CPND + PhotoND

INDC(NDS)-59+61

Moscow/Obninsk,
4-8 June 1973

9th 4C Meeting

JNDC(NDS)-54

Vienna, 16-20 Oct 1972

8th 4C Meeting

INDC(NDS)-51

Brookhaven, 25-29 Oct 1971

7th 4C Meeting

INDC(NDS)-41

Paris, 5-9 Oct 1970

6th 4C Meeting

INDC(NDS)-28

Moscow, 17-21 Nov 1969

5th 4C Meeting

INDC(NDS)-16

-6-

Summary Report
Introduction
The purpose of this Advisory Group Meeting, which was one in a series of biennial
meetings, is to review the status of the cooperation of the Nuclear Reaction Data Centers'(NRDC) Network for the previous two years and to plan for the coming two years. Afterdetailed presentations on the activities of each of the cooperating data centres, the meeting
separated into two parts, one involving the centre heads and a parallel session for discussionof technical aspects of the cooperation. The centre heads' discussion concentrated on theincreasing fiscal restraints faced by all the centres and the need to present a more coherent
view of the activities of each data centre. It was recommended to prepare a document
defining the participating data centres and outlining the special responsibilities of each centre,
in consultation with the network participants.
The technical parts of the agenda, which concentrated on the jointly operated
computerised systems and data exchange routines (i.e. CINDA, EXFOR, ENDF, etc.), took
place in separate sessions for the three specialized data centre networks for neutron reaction
data, charged-particle reaction data, and photonuclear data.
C.L. Dunford acted as chairman of the plenary sessions and of the center heads'
session. O. Schwerer acted as chairman of the technical sessions, and as the Scientific
Secretary. H.D. Lemmel, who participated at no cost to the Agency, acted as chairman of
the session on charged-particle reaction data and photonuclear data.
The meeting was attended by 20 participants from 11 Nuclear Reaction Data Centers
in USA, Russia (3), Japan (3), China, Hungary, and the centers of NEA and IAEA. See
Appendix 1 for the list of participants.
The agenda is attached as Appendix 2.
The network of Nuclear Reaction Data Centres which is coordinated by the IAEA is
responsible for the collection and dissemination of nuclear reaction data essential to thedevelopment and maintenance of applied nuclear technologies. This cooperative activity
organizes the international resources devoted to this task in order to avoid duplication andwasted effort while providing this essential service to nuclear technology research andapplication activities world-wide. This coordination has been carried out successfully formore than 25 years. Every year, technical experts from the data centres meet under IAEA
auspices to exchange ideas, develop the standards for the cooperation and determine joint
projects to be carried out. Every second year, the data centre heads join the meeting inorder to assess the cooperation and to determine the future directions of the data centres andthe network activities.
The first day of the meeting was devoted to presentation of progress reports from theparticipating centres and discussions of topic of common interest to both the centre heads andthe technical staff. The second day of the meeting was devoted to parallel sessions of thecentre heads and the technical staff representatives of the data centres. The third day was
devoted to developing the conclusions and recommendations from the meeting.

-7-

Opening Session
Mr. Ph. Savelli of the OECD Nuclear Energy Agency gave the welcoming speech on
behalf of the hosts, the NEA. He noted that the NEA had consolidated staff from three
separate facilities in the new building in which we were meeting, the Data Bank formerlyhoused in facilities provided by the French Government in Saclay. He mention the Databank priorities in the next two-year program, basic data, code certification and distribution,and evaluated data. The NEA Nuclear Science Committee initiated survey of nuclear dataneeds was completed. Response from some utilities and other users was encouraging.
Special challenges are presented because of the present declining support for the nuclear
power option. This speech was followed by the IAEA welcoming speech which waspresented by C.L. Dunford. R. Meyer made a brief statement on behalf of the USDOE andurged closer contacts between the nuclear reaction data network and the nuclear structure
data network.
The preliminary agenda was adopted after C.L. Dunford's selection as Chairman of
the meeting and O. Schwerer as Scientific Secretary. Parallel sessions were chaired by
C.L. Dunford (center heads), O. Schwerer (neutron data), and H.D. Lemmel (charged
particle and photonuclear data).
H. Lemmel gave the NDS progress report. He mentioned the staffing changes whichhave occurred in the past two years and that there were no longer any staff vacancies. The
budget reductions and staff reduction for 1995-1996 were described. The migration ofcomputing activities from the IBM to the Section's VAX was discussed with completionprojected within one year. New coordinated research programs (CRP) in nuclear model
parameters, photon production cross sections and recommended activation data were
presented.
N. Tubbs presented the NEA Data Bank report. He described the formation of the
NEA Nuclear Science Committee and its role in overseeing the Data Bank. Some disruption
in the Data Bank work occurred during the move to the new building because the facility
could not accommodate the Data Bank's computer. Thus a smaller VAX was purchased. The
use of their on-line data service is now expanding rapidly but remains at about 10% of the
NNDC activity. The new version of the European evaluated nuclear data file JEF-3 in now
being planned. The emphasis will be on advanced fuel cycles, Pu-burning and actinide
burning requirements.
Y. Kikuchi discussed the JAERI Nuclear Data Centre. Japan is a member of the
NEA Data Bank and therefore relies on it for most services. The data centre concentrates
on the coordination and production of the Japanese Evaluated Nuclear Data file, JENDL.
Version 3.2 of the JENDL General Purpose library will be released soon. Future work willconcentrate on a high energy library, minor actinides and covariances. Work continues onan artificial intelligence approach to nuclear data evaluation wherein the past experiences as
to code selection and input parameters are stored in a computer file. High energy data
evaluations are being done in support of the Omega project. They are investigating on-line
access to the centre's data. For this purpose, a workstation will be required.

-8-

M. Bhat gave the report for Brookhaven's NNDC. The NNDC has been reduced by
5 senior and 2 support staff in the past two years. The budget for the fiscal year 1995
beginning in October 1994 will be further reduced by about 40%. The VAX-clustercomputer used by NNDC has been replaced by a DEC ALPHA-7100. While traditionalrequests for nuclear data have declined, the number of retrievals supplied via the on-line
serviced is increasing rapidly. BNL is proposing to increase their nuclear reaction data
activities with two new positions. M. Bhat is not sure how this can be accomplished within
the proposed budget.
V. Manokhin of the Obninsk Nuclear Data Centre stated that FEI Obninsk had been
designated as the Russian nuclear power centre. This designation has strengthened thecentre's future prospects. The centre is interested in dosimetry data, activation libraries andcovariances. They are working on improved evaluations for Fe, Ni and Cr in conjunction
with the Chinese Nuclear Data Centre.
Zhuang Youxiang reported on the Chinese Nuclear Data Centre. The main activitiesof the CNDC include the Chinese evaluated nuclear data library CENDL (version 2.0 was
completed in 1992, 2.1 will be finished in 1995). A Chinese Evaluated Nuclear Parameter
Library (CENPL) has been preliminarily established. The centre is also active in thedevelopment of nuclear model codes as well as in the compilation and evaluation of charged
particle and photonuclear data.
M. Chiba gave the report on the Japan Charged-Particle Nuclear Reaction Data Groupon behalf of H. Tanaka. They maintain their NRDF database which has a wider scope than
EXFOR. Other main activities of the group include the translation of the relevant parts of
NRDF into EXFOR format, the development of a combined index database for NRDF and
EXFOR, and, with increasing emphasis, customer services.
Y. Tendow described the work of the RIKEN Nuclear Data Group (Japan). This
group is active in the compilation of certain charged-particle reactions in EXFOR (mainly
data for medical purposes) and also in nuclear structure and decay data as a member of theJapanese ENSDF working group.
F.E. Chukreev discussed the CAJAD nuclear data centre (Kurchatov Institute,
Moscow), the centre in charge of coordinating the CPND compilation in EXFOR. The
emphasis of their compilations is radioisotope production (in particular for medical purposes),
integral data needed for transmutuation of radioactive waste, and some data forthermonuclear fusion.
V. V. Varlamov reported on CDFE (at Moscow State University), the main data centre
for photonuclear data. So far CDFE has compiled about 500 photonuclear data works in
EXFOR. Other activities include the conversion of the photoneutron data file by E.G.Fuller(USA) into EXFOR format, photonculear data evaluation (evaluated photoneutron crosssections for O-16, Si-28, Pr-141, and Pb-208 were compiled recently in EXFOR), and thedevelopment of a new ENSDF search system for PC, NESSY.

-9F. TaYkanyi summarized the work of the Debrecen Nuclear Data Group (at the
ATOMKI Institute, Debrecen, Hungary). The group is active in measurements of excitation
functions of charged-particle induced reactions, in particular of monitor reactions and isotope
production for medical use, and is also studying new applications like the thin layer
activation technique. Their first EXFOR compilations will be distributed in September.
The progress reports are reproduced in Appendix 8.

General Discussions
After the actions from the previous two meetings were reviewed, the meeting had ageneral discussion on customer services. One major problem faced by all centres was poorly
defined requests asking for more information than could realistically be needed. It is
important that each centre have someone technically qualified to assist the requester in
defining a request more precisely. Data centres provide an important value added service
by processing raw data into a form most useful for the requestor. All centres need postprocessing capability.
The meeting agreed that the centres should adopt common graphics software so thatplotting and other codes requiring graphics can be exchanged. The on-line data services areimportant. NNDC and NDS will continue to cooperate in the development of their common
system. NNDC and NDS have been ask to install this software on the new DEC ALPHA
computer being installed by FEI Obninsk. Finally, the four neutron data centres agreed to
explore how they could share the task of maintaining a current address list database.

Joint documents distribution
For many years there had been a cooperation between the International Nuclear
Committee (INDC) and the Nuclear Data Committee of the NEA (NEANDC) on a joint
distribution of nuclear data related reports such as annual progress reports, lab reports onimportant nuclear data activities, meeting proceedings, and others.
These reports used to serve as an important information medium on an international
level among nuclear scientists. Some time ago, the NEANDC was discontinued, and thesuccessor, the NEA Nuclear Science Committee (NSC) did not take up this reports
distribution activity. Consultation will have to continue until the distribution of progressreports compiled from NEA countries has been reorganized.
It will be essential that the centers coordinate their address files and, possibly, find asolution for a jointly maintained address file for the distribution of reports and othermaterials.

- 10-

Evaluated data libraries
The status of the main evaluated neutron data libraries was briefly reviewed. For
ENDF/B-6 some updates can be expected in 1995. The JEF library (current version is 2.2,
dating from February 1992) will not be modified until the release of JEF-3 (not before 1997),
although some special purpose files will be updated (but not released) earlier. The current
version of BROND is still 2.1. Any further updates prior to the release of BROND-2.2 arefor use for FENDL purposes only. The next version of CENDL will be released in 1995.
The revision of JENDL (JENDL-3.2), now in ENDF/B-6 format, is almost completed(release was expected by June 1994).

Next NRDC meetings
The meeting envisaged the following possible dates for the next two NRDC meetings:
Next Technical NRDC meeting: Vienna, April or May 1995
Next full NRDC meeting: Brookhaven, April or May 1996

-11 -

Centre Heads Discussions
R. Meyer from USDOE presented the US nuclear data program plans. The nuclear
data budget for the US was 9.1 million dollars in 1993, is 7.0 million for 1994 and will be
6.0 million in 1995, a reduction of 1/3. The brunt of the reduction has been bourne by themeasurement program and the nuclear data centre at BNL. The nuclear data program ismanaged from an organization which is oriented toward basic science. It is difficult for themto define and get support from the user community. J. Dairiki then gave a brief summaryof the directions being taken by the nuclear structure portion of the nuclear data program,emphasizing the attempt to get new user communities involved and to make data available
through user oriented PC software.
The importance of the archival functions of data centres is often overlooked. The
longer term prospects for the NNDC and the US nuclear data program were of great concern
The potential for loss of data and expertise was serious.
Most of the remaining time was devoted to a proposal from the NEA to reorganize thestructure of the cooperation with the IAEA and the NEA having joint responsibility for thecoordination of all nuclear data activities. The NEA proposal has four main points,
1) Joint NEA-IAEA sponsorship/coordination,2) Adopt the existing infrastructure,3) Define a broader scope of activities,
4) Recognize the specialized nature of each participating centre.
Many participants supported the desire to give a more formal framework to thecooperation. Only one or two bilateral agreements exist, those being quite old and probably
not reflecting the breadth of the current cooperation. Such a document would be useful togive an official status to the participants and provide a basis for individual discussions withhigher levels of management. Some expressed concern that more tasks would result but thebudgets would not appreciate.
The proposal to replace the IAEA coordination with a joint NEA-IAEA umbrella wasmost widely discussed. Y. Kikuchi pointed out that the Japanese Government might worry
about the decreased quality of the services from the NEA Data Bank if the special role of the
US and Obninsk data centres were deemphasized. The US is a member of NEA but not theData Bank as the NNDC serves the full service data centre role for the US. C.L. Dunford
expressed concern for the practical implications of the joint NEA/IAEA coordination
proposal. In particular, the NEA is a regional organization whereas the IAEA is truly
international. NEA cannot deal officially with countries which are not members. The NEA
has responsibility for coordinating nuclear data evaluation activities through a working partyof its Nuclear Science Committee. It is not clear how the IAEA and the NEA could share
responsibility for a Working Party of the NEA.
The meeting agreed on a text on the "Coordination of Activities within the International
Nuclear Data Community", which is given on the following page. It includes a schedule fordrafting a new agreement. There is an action on the NEA Data Bank and the IAEA Nuclear
Data Section to complete a draft protocol by mid-September.

- 12-

Coordination of Activities within theInternational Nuclear Data Community
The meeting recognised:••that the only existing cooperative arrangement (from 1968) is outdated and does notdescribe the present broad scope of the cooperation in nuclear data,
the need to formulate a new agreement, reflecting:- the widened scope of the present cooperative arrangement,- the existing well coordinated efforts,- the unique expertise of the various cooperating data centres.

•

the difficulties caused by the continuous reduction of resources available to perform thevital work of the centres.

•

the need to delineate what expertise individual national data centres provide as effective
core activities of the international data effort.

•

the urgent need for a clear and concise description of this cooperative activity forreview by various administrative bodies.

The meeting recommended:•that a document be prepared, reflecting the broad scope of current and future network
activities,•

that the document include a concise definition of the objective of the nuclear data
network and the means by which the cooperative activity will be carried out,•that the participating centres and their responsibilities be clearly stated,•that the document would be regularly reviewed and updated to reflect changes in theparticipating centres and their responsibilities.

The meeting adopted the following timetable for implementing these recommendations:•comment and suggestions in writing from the participating centres to IAEA and NEA
simultaneously by 15th July 1994,•

draft agreement prepared jointly by IAEA and NEA to be circulated to participating
centres by 16th September 1994,•

IAEA should convene a meeting in Vienna during the month of October 1994, to
prepare the final version of this document and to recommend its distribution andimplementation.

- 13-

Technical Discussions
On the second day of the meeting, technical discussions were held in parallel to the centre
heads' discussions, dealing with the jointly operated computerized data systems (EXFOR,CINDA, common dictionary database). The joint operation of these systems is co-ordinatedby the IAEA Nuclear Data Section; however, any changes and updates, e.g. to accomodate
new data types, need approval at a data centres' meeting. The problems covered at thismeeting included a major revision of the EXFOR/CINDA dictionary database, dictionary andmanual updates, corrections of transmitted data, new media for data exchange, and manyothers. The technical discussions resulted in a list of more than 70 detailed technicalconclusions and actions which is given in Appendix 3.
The information exchange and data file exchange between the centers is increasingly
done by electronic media. A list of updated e-mail addresses is given in Appendix 4. An
updated list of electronic media available at the centers is given in Appendix 5.

Photonuclear data
The compilation work of V. Varlamov, CDFE, Moscow, which is the only active
center compiling photonuclear data, was much appreciated. It is most essential for the data
centers network that this center finds continuing support. Some EXFOR compilation rules,
which are specific to photonuclear data, were agreed at the meeting.
In addition to its data compilation activities, CDFE also produced bibliographic indexes
which have been distributed as CDFE-reports or also as INDC-report, INDC(CCP)-348.
More recently, also JAERI, Japan, has become interested in photonuclear data and produced
a CINDA-type bibliography published as report JAERI-M-93-195. A cooperation between
these two centers was agreed and a proposal for a CRP was formulated, see Appendix 6
which also includes a list of related actions.

Charged-particle nuclear reaction data (CPND)
CPND are compiled into the EXFOR database regularly by CAJaD, CNDC, and thetwo Japanese centers, whereas NNDC and IAEA-NDS compile such data only occasionallyas manpower permits.
It was appreciated that ATOMKI, Hungary, has joined the CPND network, specificallywith the goal of producing an evaluated CPND database for applications in beam monitoring
and radioisotope production. It is planned to support this work by a CRP. First EXFOR
entries compiled by ATOMKI will be transmitted soon.
It is hoped and encouraged that also the NEA Data Bank would start to compile
medium energy CPND into the EXFOR system.

- 14The main workload of the EXFOR compilation of CPND continues to be done by
CAJaD, Moscow (F.E. Chukreev). Specifically recognized was the recent compilation by
F.E. Chukreev of the many-years work done at the Nuclear Physics Institute of the
Kazakhstan Academy of Sciences under V.N. Levkovski, where 542 nuclear activitation
reactions induced by medium energy protons and alpha particles (E = 10-50 MeV) have beenmeasured.
It was confirmed that CAJaD continues to have the main coordinative function among
the charged particle nuclear data centers. Consequently, it will be vital for the network that
this center continues to be funded by its authorities.
Whereas most of the centers are primarily interested in integral CPND, JCPRG
continues to cover also differential CPND. The Japanese Nuclear Reaction Data File,
NRDF, which contains all types of charged-particle induced reaction data including
differential CPND, continues to be maintained. Those data which are EXFOR compatible,
are machine converted to EXFOR format and transmitted to the other centers. The
continuation of this activity was appreciated and encouraged.
The conclusions and actions agreed among the CPND centers are included inAppendix 3. The main goal of establishing an evaluated data file for selected CPND, wasconfirmed. A summary of data evaluation activities of the CPND centers and their topics
of interest is given in Appendix 7.
The main goal of the work of the CPND centers remains the creation of aninternationally recommended data file of evaluated CPND cross-sections for-beam monitoring,production of medical radioisotopes, andactivation of structural materials, possibly extending to higher energy ranges ofintermediate energy applications.

It was strongly recommended that the IAEA should support this activity by means of
a CRP to measure, compile and evaluate the required CPND.
This recommendation, coincides with the findings of the IAEA Specialists' Meeting on"Charged-Particle and Photonuclear Data Evaluations for FENDL", Smolenice, Slovakia,
18-21 April 1994. This meeting also issued a recommendation on the thermonuclear
reactions of hydrogen and helium isotopes, which are taken care of by another network of
institutes not represented in the CPND network of the present meeting.

- 15-

Appendices1.

List of participants

2.

Agenda3.

Conclusions and Actions resulting from the Technical Sessions

4.

E-Mail Addresses

5.

Media for data exchange between Centers

6.

Draft proposal: CRP on Photonuclear Data

7.

Data evaluation activities of the CPND centers

8.

Progress reports

9.

Working Papers

Appendix 1
IAEA Advisory Group Meetingon the Coordination of the Nuclear Reaction Data Centres
Paris, France, 25-27 April 1994 (Monday-Wednesday)
hosted by the OECD Nuclear Energy Agency
LIST OF PARTICIPANTS

CHINA
Liang Qichang
Chinese Nuclear Data Centre
Institute of Atomic Energy
P.O. Box 275 (41)
Beijing 102413
Tel.: +86 1-935-7729, 935-7830
Telex: 222373 iae en
Fax: +86 1-935-7008
E-mail: CIAEDNPD@VXIHEP.IHEP.CERN.CH
Zhuang Youxiang
Chinese Nuclear Data Centre
Institute of Atomic Energy
P.O. Box 275 (41)
Beijing 102413
Tel.: +86 1-935-7729, 935-7830
Telex: 222373 iae en
Fax: +86 1-935-7008

HUNGARY
F.T. Tark£nyi
ATOMKI Institute of Nuclear Researchof the Hungarian Academy of Sciences
Bern te"r 18/c, P.O. Box 51
H-4001 DebrecenTel.: +36 1-52-417-266
Telex: 72-210 atom h
Fax: +36 1-52-416-181

JAPAN
M. Chiba
Sapporo Gakuin University
Bunkyodai-11, Ebetsu-shi
Hokkaido 069
Fax: +81 11-386-8113
Tel. +81 11-386-8111

T. Katayama
Hokusei-Gakuen University
Dept. of Information Systems
Ohyachi W. 2-3-1
Sapporo 004
Fax: +81 11-894-3690
E-mail: katayama@orion.hokusei.ac.jp
Y. Kikuchi
Nuclear Data Center
Japan Atomic Energy Research InstituteTokai-mura, Naka-gun
IbaraM-ken 319-11
Tel.: +81 292-82-5480
Fax: +81 292-82-6122
E-mail: j2925@jpnjaeri
Y. Tendow
The Institute of Physical andChemical Research (RIKEN)
2-1 Hirosawa, Wako-shi
Saitama-ken 351-01
Tel.: +81 484-62-1111
Telex: 2962818 riken j
Fax: +81 484-62-4641
E-mail: tendow@rkna50.riken.go.jp

RUSSIA
F.E. Chukreev
Institute Atomnoi Energii I.V. Kurchatova
Ploschad Kurchatova
123 182 Moscow
Tel.: +7 095-196-1612
Telex: 411594 shuga su
Fax: + 7 095-943-0073
E-mail: chukreev@cajad.kiae.su

-2V.N. Manokhin
Centr po Jadernym Dannym
Fiziko-Energeticheskij Institut
Ploschad Bondarenko
249 020 Obninsk, Kaluga Region
Telex: 911509 uran su
Fax: + 7 095-230-2326
E-mail: manokhin@cjd.obninsk.su
V. Varlamov
Centr Dannykh Fotojad. Eksp.
Nauchno-Issl. Inst. Jad. Fiz.
Moskovskij Gos. Univeersitet
Moscow V-234
Telex: 411483 mgu su
Fax: + 7 095-939-5034
E-mail: cdfe@compnet.npimsu.msk.su

UNITED STATES OF AMERICA
M.R. Bhat
National Nuclear Data Center
Bldg. 197DY
Brookhaven National Laboratory
Upton, N.Y. 11973
Tel.: + 1 516-282-2814
Telex: 6852516 bnl doe us
Fax: + 1 516-282-2806
E-mail: nndcmb@bnl
J. Dairiki
Table of Isotopes Project
Bldg. 70A, Room 3307
Lawrence Berkeley Laboratory
University of California
Berkeley, CA 94720
Tel.: + 1 510-486-5673
Fax: + 1 510-486-4808
E-mail: dairiki@csa5.lbl.gov
V. McLane
National Nuclear Data Center
Bldg. 197DY
Brookhaven National Laboratory
Upton, N.Y. 11973
Tel. + 1 516-282-2902
Fax: + 1 516-282-2806
E-mail: nndcvm@bnl

R.A. Meyer
Div. of Nuclear Physics
ER 23/GTN
U.S. Department of Energy
Washington D.C. 20585
Tel.: + 1 301-903-3613
Fax: + 1 301-903-3833
E-mail: u7552rm@doeer

INTERNATIONAL ORGANIZATIONS
IAEA
C.L. Dunford
IAEA Nuclear Data Section
Wagramerstr. 5, P.O. Box 100
A-1400 Vienna, Austria
Tel.: +43 1-2360-1709
Fax: +4343 1-234564
E-mail: rnds@iaeal
H.D. Lemmel
Tel. +43 1-2360-1717(address as above)
O. Schwerer
Tel.: +43 1-2360-1715(address as above)
NEA
C. Nordborg
OECD/NEA Data Bank
Le Seine Saint-Germain
12 boulevard des lies
F-92130 Issy-les-Moulineaux, France
Tel.: +33-1-452-41092
Telex: 620160 oecd f
Fax: +33 1-45-24-1110
E-mail: nordborg@nea.fr
M. Konieczny(address as above)
N. Tubbs(address as above)
P. Nagel (part-time)(address as above)

Appendix 2
IAEA Advisory Group Meetingon the Coordination of the Nuclear Reaction Data Centres
Paris, France, 25-27 April 1994 (Monday-Wednesday)
hosted by the OECD Nuclear Energy Agency
AGENDA

Plenary session
P. 1 Opening, election of chairmain
P.2 Adoption of the agenda
P.3 Brief status reports of the centres
P.4 Review of general actions fromthe last Technical NRDC meeting (INDC(NDS)-279, p. 7) andthe last Center Heads' Meeting (INDC(NDS)-262, p. 13)
P.5
Customer services
P.6
Documents distribution
P.7
Online systems and other new technologies
P.8
Evaluated data libraries
P.9
Next NRDC meetings
Technical meeting 1995
- AGM in 1996

Centre heads session, neutron data centres
general situation, manpower
customers and role of the centers, future developments

Centre heads session, all data centres
similar as for neutron data centers

Technical session (all data types)
T.I
New transmission format for EXFOR/CINDA dictionaries
T.2
Media for data exchange between centres (tapes, diskettes, e-mail, FTP)
T.3
Review of actions on EXFOR from last Technical NRDC meeting,
INDC(NDS)-279, pp. 8-10
T.4
Pending EXFOR matters (dictionary and manual updates, coding rules)
T.5
TRANS tapes transmitted since last meeting
T.6
Distribution of TRANS tapes
T.7
Common graphics software

Technical session (Photonuclear Data)
TP.l Data compilation and evaluation
TP.2 Bibliography: CDFE + JAERI cooperation?

-2Technical session (CPND)
TC. 1 Review of data needs for applications
TC.2 Compilation and evaluation

Technical session (Neutron data)
TN.l Sharing of address list information
TN.2 Review of actions from last Technical NRDC meeting
TN.3 CINDA
TN.4 Neutron EXFOR compilation and completenessFinal plenary session
FP1. Summary and conclusion of the Center heads sessions
FP2. Summary and conclusions of the technical sessions
FP3. Summary and conclusions of the plenary session
FP4. Other businessFP5. Closing of the meetingAppendix 3
IAEA Advisory Group Meeting on the
Co-ordination of the Nuclear Reaction Data Centres
Paris, France, 25-27 April 1994

CONCLUSIONS and ACTIONS
resulting from the Technical Sessions
E-mail and data Hie exchange between centres
1) Concl.

The updated list of e-mail addresses as compiled at this meeting isnoted (see Appendix 4)

2)The list of accepted/preferred media for data exchange between thecentres as compiled at this meeting (see Appendix 5. WP 6 as
updated at this meeting) is noted and will be applied for theexchange of CINDA batches, EXFOR TRANS tapes and CP/4Cmemos.

Concl.

EXFOR/CINDA Dictionaries
3)

Concl.

A new "super-dictionary" based on the existing DANIEL internal
dictionary system already used at NNDC and NDS, and including
free text information as given in the current EXFOR/CINDA
dictionaries, will be developed.
This will be the Master
dictionary, from which it will still be possible to produce
dictionary transmission tapes in the traditional (IBM) format.

4)

Act. NDS

Make sure that all information necessary to produce EXFOR
dictionaries is present in the new Master file.

5)

Act. McLane

Write the program needed to produce new EXFOR/CINDA
dictionaries in the traditional format from the new Master file.

6)

Act. NDS

Continue sending dictionaries in traditional format to all centres
that need them.

7)Act. McLane

Send EXFOR checking codes (executables only) plus theaccompanying dictionaries (in DANIEL format) to NEA.

8)

Concl.

Upper and lower case should be allowed for expansions in
dictionary columns 12 to 66.

9)Act. NDS

Add the code O-G-0 to dictionary 36.

-2EXFOR, general
10) Concl.

Status of Dubna institute is "International".

11) Act. CJD

To inform NDS whenever an institute name is changed.

12) Act. McLane

To update and submit dictionary 36 entries on photonuclear
quantities (with expansions) and to make appropriate changes in
LEXFOR entry. (See memo CP-C/200 and reply in CP-D/219)

13) Act. McLane

To provide Lexfor entry for energy spectra of particle pairs andPAR,SIG,P/T

14) Act. NDS

Following item (11), to update dictionary 36 accordingly, possibly
introducing longer expansions for these quantities.

15) Act. McLane

If staffing permits, update the EXFOR manual.

16) Act. NNDC

Send the remaining entries from EXFOR files 6,7,8 to the otherneutron data centres.

17) Act. All

Go through these entries and decide which entries need conversion
to EXFOR.

18) Act. All

Retransmit those entries listed in V. Mclane's list of pending
retransmissions.

19) Act. NNDC

To update the EXFOR manual Chapter 7 (dictionaries) on
dictionary 6: how to invent report codes for annual reports without
a report code on the cover. Accepted procedure is A-(3-digit
labcode from dict.3, e.g. A-ALB-.).

20) Concl.

Proposed codes for Diet. 36, IND,ZP and CUM,ZP (Memo
4C-4/55) are rejected, based on the reasons given in Memo
CP-D/245.

21) Act. CJD

Retransmit the entry (referenced in Memo 4C-4/55) with modified
codes.

22) Act. NEA-DB

Review entry 22206 in TRANS 2132 to check whether either anerror has been made in the reaction coding, or whether it is a newdata type needing new coding.

23) Act. Manokhin

Circulate the latest memo regarding the conference
93DUBNSP

code

-324) Concl.

General structure of the BIB section: - if both coded informationand free text are given for a keyword, it is legal and often
necessary to start with free text and give the code(s) only in one of
the following lines.

25) Act. McLane

Clarify wording on free text in the EXFOR manual.

26) Act. McLane

Add a note in the EXFOR manual on the possibility ofretransmission of entries belonging to a centre which is no longer
active in a this type of data.

27) Act. CAJaD

Correct and retransmit Munzel data (see Memo CP-A/65).

28) Act. CDFE

Correct and retransmit L series entries (see Memo CP-A/65).

29) Act. NDS

Correct the explanations for the codes BRA and BRS in Diet. 34,
and add the reference MSU- INP- to Diet. 6 (see Memo CP-M/15).

30) Act. Chiba

Retransmit TRANS tapes E010 and E011 with the corrections
requested by NDS.

31) Act. All

Note common errors in EXFOR entries pointed out by
O. Schwerer.

32) Act. NNDC

Submit a dictionary 6 code for CRR.

33) Act. NDS

Provide NEA-DB with an expanded list of errors in old entries
from area 2 needing retransmission.

34) Act. NDS

Retransmit entry 22242 with an EXFOR G-series number.

35) Concl.

NDS will compile EXFOR entries from Chinese works publishedin English in the Chinese Journal of Nuclear Physics. All otherworks will continue to be compiled by CNDC.

36) Act. NDS

NDS will periodically send CNDC supplementary EXFOR data in
the form of LB***.TLB and RED.LB* files to update their
EXFOR master library.

37) Concl.

The distribution of EXFOR TRANS tapes is revised according to
the following scheme:-

Each of the 4 centres producing neutron-EXFOR TRANS tapes(NNDC, NEA-DB, NDS, CJD) will continue to send theirtapes to each of the other 3 centres.

-

All other centres (CAJAD, CDFE, CNDC, RIKEN, Sapporo,
Debrecen) will send their "non-neutron" TRANS tapes only to
NDS.

-4NDS will, after checking them, send these "non-neutron" tapes
to all centres needing the particular data type:
NNDC:
NEA-DB:
CJD:
CAJaD:CDFE:
CNDC:
RIKEN:
Sapporo:Debrecen:

all data types
all data types(only receives neutron data)
CPND only
PhotoND only
all data types
none
CPND only
CPND only

Fission-product yield data
38) Act. NNDC
andNDS

EXFOR retrievals by fission-product nuclides should be possible.
While the NDS EXFOR index provides this possibility, it is not yet
possible in the VAX EXFOR retrieval system, which should be
updated accordingly.

39) Act. Lammer

To revise the LEXFOR entry on FP yields.

40) Act. CJD

To send the ASIYAD-MIFIFPY library with brief documentation
to NDS (for distribution).

41) Act. Lammer

Submit a proposal on the coding of mass yields as a CP memowith information on corresponding measurements.

CINDA42) Act. NEA-DB
and NNDC

To update the CINDA manual and the EXFOR manual withinformation about using diskettes (which format and density etc.)
for EXFOR/CINDA transmissions.

43) Act. NEA-DB

Update CINDA manual to show that blank E-MIN field is now
permitted.

44) Act. Lammer
and McLane

Review memo 4C-3/374 once more and submit jointly a newwording for the proposed CINDA manual update.

-5Evaluated Data Libraries
45) Act. All

When preparing evaluated data libraries, characteristic values(thermal cross sections, resonance integrals, etc.) should be quoted
in the text or in accompanying documents together with theiruncertainties: however, these values (and uncertainties) would bebetter usable if they were in a computer-readable file.

46) Act. All

To collect lists of known faults in the evaluated data libraries,
communicate these lists to the other originators data centres,
possibly to include such lists in a forthcoming issue of NNDEN.

47) Act. Liang

To submit memo CNDC-025/04/94-001 on format changes in
ENDF/B to R. Roussin (RSIC) who is in charge of the format-andprocedures subcommittee. As any format change requires a seriesof programming changes, it is essential that a proposal for a formatchange is supported by a convincing justification, demonstrating
the deficiency in the present format and the advantages of the
proposed format.

48) Act. NDS

NDS will send CNDC updated versions of the main evaluatedlibraries.

Charged-Particle Nuclear Data
49) Concl.

The responsibility for the coordination of the compilation ofexperimental CPND in EXFOR remains with CAJaD as laid downin the conclusions of the previous meetings, with the following
additions:-

Debrecen compiles data measured in Hungary and in Julich;and old data needed for evaluation.

-

the NEA Data Bank has started compilation of which the list of
papers was communicated to CAJaD.

50) Concl.

The following centers are now involved in CPND evaluation:(see table in Appendix 7)51) Concl.

Coordination of the evaluation activities must be organized, by
mutual information, and through IAEA/NDS.

52) Act. NDS

IAEA should give high priority to a CPND CRP for which
proposals have been worked out (to be appended to the Minutes).
The proposals will be reviewed by the INDC in early 1995.
Depending on financial resources the CRP could start in 1995/96.

-653) Concl.

Further CPND coordination should be done at the Technical
NRDC Meeting April/May 1995.

54) Concl.

Attention was drawn to the newly published CPND compilationsin Landolt-Bornstein, New Series, vol. 13, and in the NUCLEX(or similar name) database to be presented end of May in Paris.
It is believed that both are by the same Russian group of authors.

55) Act. NDS

To contact the authors of the Landolt-Bornstein CPND compilation
to obtain a computer file of this database for free distribution, andto find out whether and how this group can contribute to the
network in future.

56) Concl.

An evaluated CPND file in ENDF-6 format shall be started for
CPND applications. The first entry on p + F e has been completedby CNDC.

57) Act. CNDC

To send this file to NDS.

58) Act. Debrecen
and CNDC

Evaluations at Debrecen have been completed. They should be put
in ENDF-6 format in cooperation with CNDC.

59) Concl.

The work by CAJaD (Chukreev) to compile the Levkovski data
(i.e., more than 500 subentries) was highly appreciated. Gratefulcomments by data users have been received.

60) Act. Mclane

Try to find time to compile and distribute, after consultation with
F. Chukreev, the EXFOR converted CPND file of R. White(Livermore) on light-element neutron-producing reactions.

61) Act. NDS

Contact Arzamas to obtain the quasi-EXFOR file of experimental
data underlying the Arzamas evaluation.

62) Act. CAJaD,
CNDC,
RIKEN,ATOMKI

Inform other centres of plans for evaluation and compilation ofmonitor reactions and of medical radioisotope production reactions,through regular consultation.

63) Act. Dunford

Produce a "Short guide to ENDF" for evaluators of integral
charged particle data and send it to Dr. Chukreev.

64) Act. CAJaD

Send a list of references of publications needed but not available,
to NDS who will try to deliver copies of those publications.

65) Act. CAJaD

Request assistance from other centres in case of difficulties incontacting authors.

-766) Concl.

The centres involved in CPND work should concentrate on thecompilation and evaluation of old /existing data.

67) Concl.

Current data most commonly exists in the form of books. The data
centres need this data in computational and graphical format.

68) Concl.

The centres will continue to compile data from their own
geographical regions (China, Japan, Russia), as agreed previously.
For other countries it is important to find agreements which avoid
parallel efforts or replication of work.

Photomiclear data69) Act. NEA-DB

Find out whether NEA, NDS, NNDC can obtain the data filecontaining the bibliographic data on photonuclear data.

70) Act. CDFE,
JAERI,
CNDC, CJD

See Appendix 6 for a work program in support of the proposed
CRP on Photonuclear Data.

Next NRDC meetings71) Concl.

The meeting envisaged the following possible dates for the next
two NRDC meetings:
Next Technical NRDC meeting: Vienna, April or May 1995
Next full NRDC meeting: Brookhaven, April or May 1996

72) Act. All

To propose topics for the next Technical NRDC Meeting, e.g.,-

meeting of programmers for the online system?

-

common graphics systems (would require beforehand theexchange of experiences with graphics systems)?

-

CPND workshop for an evaluated data file?

Appendix 4

E-Mail Addresses

NEA:
INTERNET

Konieczny@NEA.FR

BITNET

Konieczn@FRNEAB51

X-400 (Atlas)

C=FR, A=ATLAS, P=NEA, S=name

X25 (Transpac)(208) 092 160 775 1(or any other staff member name in place of Konieczny)

NDS:
INTERNET

Schwerer@IAEAND.IAEA.OR.AT(or any other staff member name in place of Schwerer)
BITNET

RNDS@IAEA1

INTERNET

Tendow@RKNA50.RIKEN.GO.JP

INTERNET

Chiba@NUCL.PHYS.HOKUDAI.ACJP

INTERNET

Katayama@EDVZ.KFUNIGRAZ.AC.AT

Y. Tendow:

M. Chiba:

T. Katayama:(from 1st April 1994 to 31st March 1995)

Qichang Liang:
INTERNET

CIAEDNP@BEPC2.IHEP. AC. CN

-2Youxiang Zhuang: (changed as of August 1994)
INTERNET

CIAEDNP@BEPC2.IHEP.AC.CN

INTERNET

h3817tar@ELLA.HU

INTERNETmclane@BNLND2.DNE.BNL.GOV

Ferenc Tarkanyi:

V. McLane:

nndc@BNL.GOV (central mailer)

F.E. Chukreev:
INTERNETchukreev@CAJAD.KIAE.SU

INTERNET

cdfe@COMPNET.NPIMSU.MSK.SU

INTERNET
BITNETkikuchi@CRACKER.TOKAIJAERI.GO.JP
J2925@JPNJAERI

V. Varlamov:

Y. Kikuchi:

Working Paper 6: Media for data exchange between Centres
Please indicate which center can accept what media for the various types of data. If more than one medium is acceptable, the preferred one is in bold.
B= e-mail (Bitnet)

TI= e-mail (Internet)

D5 = PC diskette 5 !4 inchF

= FTP (Internet File Transfer)

D3 = PC diskette 3V4 inch

NNDC

NEA-DB

NDS

CJD

Cinda
batch

I, F

I,
F, D3, DS,(B, T)(B), I,(F, D3, D5)

B(D3, D5)InterimDiet, update

I,F

any

EXFOR
TRANS

I, F, CO.
D5, D3I,F,
D3, D5,(T)

CP-Memosand
4C-MemosI,
all

H, B, IH

= conventional magnetic tape

CAJaD

CDFE

= hardcopy

CNDC

REKEN

SapporoDebrecen~T(H, D3, D5)*)

D3, DS,
T, I

D3, D5D5H, I, B,T, D3, D5

B, I, F,
H

T, F, D3,
D5

T, D3, D5

D3, D5,
T

D3, D5

T

T, D3, D5
F

T, F,
(D3)

D3, D5,T

H, B,I

H,B

H, I

B, I (soon)
H

H, D5

H, I, B

H, I,
B

H,B,
I

If data are sent in zipped (compressed) mode on diskette, the unzipping code should be included on the diskette.
*) To be confirmed by CJD

1Appendix 6
DRAFT PROPOSAL

Coordination Research Program
Photonuclear Data : Compilation and Evaluation(Y. Kikuchi, V. Varlamov, Zhuang Youxiang)

Photo-induced reaction data is required for various fields including both basic andapplied research.
Many laboratories use gamma rays for performing activation analysis of minerals,ores, coal, and other bulk materials for industrial applications using different sources ofgamma radiation. Other areas where accurate photonuclear data are needed, are reactor incore dosimetry, radiation damage estimates in reactor structural materials, and safeguards.
Photonuclear data are also important for thermonuclear reactors, because they have
implications for plasma diagnostics, structural integrity, and personal safety.
Primarily, evaluated data on photonuclear reaction cross sections for the majority ofnatural isotopes (C, N, O, Al, Si, Ge, Ti, Fe, Ni, Cu, Ta, Pb, W, Bi, etc for constructing,shielding, medicine, electronics, etc), some transuranic nuclei (Th, U, Pu, Np, Am, etc for
nuclear fuel, nuclear waste, etc) and several fission products are needed.
Unfortunately, specialists working in these fields are using "raw" photonuclear data,primarily, reaction cross section data from different (and often discrepant) measurements
because of the absence of evaluated data sets.
It is difficult to produce the complete photonuclear data file on the basis of theevaluation of measured cross sections only:-

there are not sufficient experimental data necessary for the evaluation in a numberof interesting cases;-

much experimental photonuclear data is obtained by different kinds of photon
sources and significant systematic uncertainties are presented.

Therefore, a coordinated research program (CRP) with the purpose of thedevelopment of the evaluated photonuclear data library is very desirable.
Large scale evaluations of this kind are going on now in the Centre for Photonuclear
Experiments Data (CDFE) of MSU INP and in the Centre of Nuclear Data (CJD)
Photonuclear Working Group in Russia, in the Japanese Nuclear Data Committee
Photonuclear Data Working Group, and in the Chinese Nuclear Data Centre.

-2This CRP should be supported by the following work program of the data centers.
1.

CDFE, JAERIThe creation of an international photonuclear data index, perhaps,
based on the indicies currently produced in JAERI and CDFE.

2.

CDFE

The compilation of experimental photonuclear data, primarily
photoneutron reaction cross section data, using the EXFOR system.

3.

CDFE, JAERI

Detailed comparison of the experimental methods using different
photon beams (bremsstrahlung, quasimonoenergetical, tagged, etc.)

4.

CDFE

The improvement of the methods for evaluation of photonuclear dataobtained in experiments of various kinds.

5.

JAERI, CNDC, The improvement
CJD
photonuclear data.

6.

CDFE, JAERI

Identification of disturbing disagreements between experimental dataand submission of such cases to the CRP to perform newmeasurements.

7.

JAERI, CJD

The development of files of evaluated photonuclear data using the
EXFOR and ENDF systems.

8.

CDFE

Updating of old versions of photonuclear data files.

oftheoreticalmodelsforcalculationof

The main participants of this CRP should be:
1

The Centre for Photonuclear Experiments Data (CDFE) of the MSU INP, Moscow,
Russia, Dr. V. Varlamov.

2.

The JAERI Nuclear Data Centre in coordination with the Photonuclear Data Evaluation
Working Group of the Japanese Nuclear Data Committee, Drs. Y. Kikuchi, N. Kishida.

3.

The Chinese Nuclear Data Centre (CNDC), Beijing, China, Dr. Zhuang Youxiang.

4.

The Nuclear Data Centre (CJD) Photonuclear Data Working Group, Obninsk, Russia,
Dr. A. Blokhin.

Additionally, the following specialists (experts) could be invited to participate this CRP:
1.

Drs. S.I. Warshaw, R.M. White, R.A. Alvarez
Lawrence Livermore National Laboratory, P.O. Box 808 Livermore, California 94550,
USA

-32.

Prof. E. Hay ward
National Institute of Standards and Technology, Washington, D.C. 20234, USA

3.

Prof. D J . S . Findlay
Materials and Manufacturing Technology Division, B 418.15, AEA Industrial
Technology, Harwell Laboratory, Oxfordshire, 0X11 ORA, United Kingdom

4.

Prof. J. Ahrens
Inst. fur Kernphysik, Joh. Gutenberg-Universitat, D-6500 Mainz, Germany

5.

R. Van de Vyver
Laboratorium voor Kernfysika Rijksuniversiteit, Proeftuinstraat 86, B-9000 Gent,
Belgium

6.

M.N. Thompson
School of Physics, University of Melbourne, Parkville, 3052, Victoria, Australia.

7.

E. Wolynec
Instituto de Fisica, Universidade de Sao Paulo, Caixa Postal 20516, Sao Paulo, 01498,
SP, Brasil

Data evaluation activitiesof the CPND centers
CAJaD
light c.p.
fusion reactions
reactions forbeam monitoring
reactions for
medicalradioisotopes

CNDC

Debrecen

X

exp.

X

X

X

X

X

X

compile(Gu-ZhovskiXdifferential CPND

*)

JAERI

NEADB

RIKEN

FENDL coop.

compilecompilesomecompilationX1.) up to
50 MeV2.) higher
up

partly up to
100 MeVcompile,code
comparison

futurein-beam data foruse of accelerators(a,n)

IAEANDS

X

thin layer
activation (TLA)
higher energy data
for transmutation

Hokkaido

X*)

X
NRDFto
EXFOR
conversion(a,n): PC code and evaluated data file available at CAJaD for detecting
actinides in soil (Chernobyl); in Russian, could be issued in English.

aIAppendix 8

Progress Reports

Rl

NNDC status report

R2

OECD NEA Data Bank status report

R3

IAEA NDS progress report

R4

The CJD status report
V.N. Manokhin

R5

CNDC status report
Zhang Jingshang, Zhao Zhixiang, Zhuang Youxiang, Liang Qichang

R6

Status report of JAERI/JNDC and JNDC
Y. Kikuchi

R7

Japan charged-particle nuclear reaction data group
status report
H. Tanaka

R8

Status report of the RIKEN nuclear data group
Y. Tendow

R9

Charged particle reaction data compilation and evaluation(CAJaD)
F.E. Chukreev

RIO

The MSU INP CDFE activities in photonuclear data compilationand evaluation and in EXFOR, ENSDF, and NSR
I.N. Boboshin, V.V. Varlamov, N.G. Efimkin, V.V. Sapunenko,
M.E. Stepanov

Rl 1

Status of the Debrecen nuclear data group

Rl
NATIONAL NUCLEAR DATA CENTER
Status Reportto theAdvisory Group Meetingon the Co-ordinationof the Nuclear Reaction Data Centers
25 - 27 April 1994

GeneralSince the last meeting of the Nuclear Reaction Data Centers in October 1991, our staff has been
decreased by five scientific/professional and two support positions (there are currently 6 FTE
scientific/professional and 4 support staff). C.L. Dunford is on a two-year leave of absence;
Mulki Bhat has been named acting head of the NNDC.

Computer Facilities
In the past two years the NNDC has upgraded its computer facilities to reduce the necessary
system support. The NNDC VAX cluster has been replaced with a VAX Alpha Model 7610.
Because several minor applications have not yet been transferred to the new Alpha, the VAX
11/780 has been retained. It is expected that the VAX 11/780 will be shut down within six
months.

bibliographies
The NSR activity has continued. The publication of Recent References has been reduced to one
issue per year in the December issue of Nuclear Data Sheets.
The CINDA compilation activity continues with respect to those references associated with theexperimental data compiled at the Center.

Data Libraries
In the period from October 1991 through March 1994, 12 neutron data transmission tapes(TRANS 1245-1256) were sent containing new and corrected entries.

Evaluated Nuclear Reaction Data
NNDC continues to coordinate the work of the Cross Section Evaluation Working Group.
ENDF/B-VI, Release 2, was distributed in June, 1993, and includes updates to the neutron,
neutron fission product yield, decay data, and spontaneous fission product yields sublibraries.
Also included are additions to the high energy neutron and proton sublibraries.
Version 6.9 of the ENDF Utility codes was distributed in November, 1993.
The Symposium on Nuclear Evaluation Methodology was held at Brookhaven in September 1992.
The proceedings have been published by World Scientific Publishing Co.

Nuclear Structure Data
NNDC continues to publish the Nuclear Data Sheets.
Volume 71, #1 have been sent to Academic Press.

As of March, 1994, issues throughCustomer Services
Since October 1, 1991, use of the online data service has steadily increased. There are now morethan 1000 customer accounts with more than 1400 users. There have more than 5000-tetrievals
per month for the past several months. A chart of Online Data Service retrievals is attached.

Publications
The DOE compilation of requests for nuclear data was done at Oak Ridge and published as report
OR NL/TM-12291.

CSISRS Library Statistics
March 28. 1994

Area

# subentries# data points

Last tape added

Neutron1
2
4

17 30214 6195 122
7 151

1 725 736
1 182 412
56 204176 186

1255
2132
3090
4094

3 520
1 538
1 472
388
1 116
708
346
313

64 96916 84525 9338 815
19 074
11 619
5 098
4 134

A028
B011
CO 13
DO 17
E009
POO1
R007
S006

29
651
2 453

455
32 77264 430

G007
L004
MO 15

618

36 380VO25

Charged Panicle
A
B
C
D

E
P

R
'3~
Photonuclear
G
L
M

Q
Evaluation
V
Total

CSISRS LIBRARY STATISTICS FOR AREA 1 LISTED BY REFERENCE
Year
1988
1989
1990
1991
1992
1993
Total

# Subentries
117
118
74
90
32
31
462

# Data points
99475
10068
55345
18221
56590
8129
247,828

March 2<S, 1994

Last Transmission 1255

CSISRS LIBRARY STATISTICS FOR AREA 2 LISTED BY REFERENCE
Year
1988
1989
1990
1991
1992
Total

# Subentries
500
268
315
71
2

1,156

# Data points
15628
14984
15764
3481
1152
51,009Last Transmission 2132

CSISRS LIBRARY STATISTICS FOR AREA 3 LISTED BY REFERENCE
Year
1988
1989
1990
1991
1992
1993
Total

# Subentries
111
193
74
107
55
22
562

# Data points
1191
1568

Last Transmission 3090

499
654
599
598

5,109

CSISRS LIBRARY STATISTICS FOR AREA 4 LISTED BY REFERENCE
Year
1988
1989
1990
1991
1992
1993
Total

# Subentries
188
99
219
39
76

30
551

# Data points
3961
3224
1800
1701
1596
487

11,256

Last Transmission 4094

NNDC On-Line Data Service Retrievals
1986-1993

NSR
ENSDF
NUDAT
CINDA

I I ENDF• CSISRS
MIRD.
PLOT
PHYSCO
X-RAY
CODES
MASSES*

1986

1987

1988

* Added November, 1993

1989

1990

1991

1992 1993

NNDC On-Line Data Retrievals 1986 -1993
1986

1987

1988

1989

1990

NSR
ENSDF

814

2521

5022

3253

5613

142

863

1303

850

NUDAT

536

815

1492

CINDA

129

60
4

ENDF
CSISRS

1993

11517

1992
13050

17170

Totals
58960

1256

2807

3626

7161

18008

1841

2204

4021

6710

10984

28603

285

522

187

371

458

373

2385

187

150

1019

1525

2846

5818

11549

459

1649

1623

1384

1613

4482

11210

121

53

40

141

586

941

144

144

Other:MIRD
MASSES*
PLOT

11

39

69

218

988

1325

PHYSCO

9

65

172

96

189

531

277

1169

933

2379

873

873

—

X-RAY
CODES

Totals1621 4263* Added November 1993

8748

8406

12059

22183

29927

49701

R2

OECD NEA Data Bank
Status Report to theAdvisory Group Meeting on the Co-ordinationof the Nuclear Reaction Data Centres
April 1994

GeneralSince the last NRDC Meeting held in Obninsk in October 1991, the Data Bank has moved
from Saclay to join the rest of the NEA at new premises at Issy-les-Moulineaux. Johnny
Rosen retired after nearly thirty years as Deputy Director of Science, Computing andDevelopment, and has been succeeded by Philippe Savelli, formerly of CEA.
Overall staff levels remain largely unchanged, but available manpower has been affected bydelays in filling vacated posts, and by an increased workload caused by the addition of new
projects.

Computer Facilities
At the time of the move to Issy-les-Moulineaux the Data Bank computer was upgraded to a
VAX 6000-510, providing an 3x increase in CPU power, and a total of 19 Giga-bytes of disk
space. This has now been complemented by a network of seven workstations, including a
UNIX machine, and most recently, a VAX Alpha. Office automation is carried out on a
Micro VAX 4000, shared with the rest of the agency.
Distribution media include, VAX magnetic tapes, TK70 cartridges, 8mm video tape, UNIXcassettes, and PC diskettes. Facilities for writing Compact Discs and 4mm DAT tape are
currently being implemented.
Since the move to Issy-les-Moulineaux, the Data Bank has been connected to the highcapacity French Internet circuits, RERIF (He de France) and RENATER (International).
Network access to the Data Bank is now possible via INTERNET, BITNET, X-400 and
TRANSPAC. DECNET access has been discontinued.
To complement the possibilities of improved interactive access and file transmission, the NEA
On-Line Service has been extensively modified. A new user-friendly interface has been
implemented, facilities for guest sessions and on-line sign-on have been added, and a newservice offering electronic-mail retrievable files (Mailserver) has been introduced. In addition
to the databases traditionally offered (EXFOR, CINDA, EVA, TDB, NSR, ENSDF, NUDAT,ABSTRACTS), documents from other NEA divisions have been made available online for
consultation or electronic retrieval in a number of formats. This service is being extended toinclude controlled self-service retrieval of smaller programs, and a part of the corresponding
documentation (70,000 pages out of a total of 400,000) is being scanned for inclusion inimage form in the information available for retrieval.
The total number of user sessions rose to 3000 in 1993, with 200 registered users at the endof the year. It is expected that the number of users will double to 400 by the end of 1995.
In view of the age of the present data base programs and the limited future of DEC DBMS,
the decision has been taken to move to a multi-platform relational system. ORACLE has beenchosen. A trial in-house conversion of the EXFOR data base is under test, and a design study
has been carried out on the much larger EVA data base.

Data Services
The number of online accesses to the various nuclear data databases has steadily increased
since 1991. In 1992 the total number of data requests were 967, of which approximately 800
were by online retrieval. In 1993, the number of manual requests remained approximately
constant at around 150, but the number of online retrievals increases to 1400 as a result of
the improved online access and new online system.
For requests answered manually, there has been a notable increase in the number of requests
for data dispatched by FTP and Unix TAR format.

EXFOR
Compilation of EXFOR entries has been carried out by consultants from universities in OECD
Member countries. This arrangement has served to compensate for the limited resources atthe Data Bank, and stimulate interest in nuclear data at an academic level. Fifty-five new
EXFOR entries have been compiled since the last NRDC meeting in 1992. A further 40 to
50 new entries are expected to be compiled in 1994.

CINDA
Following a 6 month break in 1991, due to a vacant post, CINDA compilation was resumed
in 1992. The backlog was cleared and compilation continued until April 1993. Since then,manpower shortages have meant that CINDA coverage has been seriously affected, with thenotable exception of scanning work performed by JAERI, Japan. It is hoped to use external
consultants to clear the backlog and maintain coverage, in future.

JEF
The JEF-2.2 General Purpose library was released in January 1992, followed by theRadioactive Decay Data and Fission Product Yield sub-libraries in the summer of 1993.

Benchmark testing of the JEF-2.2 General Purpose data for a variety of applications
continued, and has revealed a number of areas where work is needed in order to achieve thegoal of an evaluated data library suitable for differing applications without adjustment.
However, several nuclear utilities in Member countries have already indicated their intentionof adopting the JEF file as their standard reference library.
At the JEF Scientific Coordination Group meeting in December 1993, it was decided that thecurrent JEF-2.2 file would remain unchanged at the level at which it has been tested, with nofurther updates in the near term. Future work will be oriented towards long-term
improvements leading to a validated JEF-3 library by 1997. The close cooperation between
the JEF and EFF projects will continue, and a joint JEF-EFF library, based on JEF-3 andEFF-3 , is still envisaged.
Following a recommendation of the JEF Scientific Coordination Group, it was decided at theNovember 1992 meeting of the Nuclear Science Committee, that the JEF-2.2 General Purpose
Library was suitable for distribution to scientists outside the OECD area, especially in viewof the extension of the NEANSC International Evaluation Cooperation to include non-OECD
economies.
In order to make JEF data available to a wider range of data users, and in particular to users
in non-energy applications who have no experience with the ENDF-6 format, a PC programfor displaying JEF decay, fission yield, and cross section data has been developed incollaboration with Birmingham University (UK) and Orsay University (France). This package
will become available in June 1994. An earlier version containing only JEF decay data has
been available since July 1993.

VAX Configuration NEA DB (Issy)
Monday, 7 June, 1993

2 videotape units
5 GB

IZ tape units\
6250 bpi

19 GB disk

OECD Washington I
DC

1500 disk I/O
per second

OECD
Tokyo

128 kbaud

Officeautomation
server

64 kBauds

OECD
Headquarters

DECNET 19.2kbauds

A
VAX 6510
128 MB
15 MIPS

VAX 4000/200
48 MB
5 MIPS

EARN
BitNetInternet

TRANSPAC 19.2Kbauds

CRAY-XMP
CRAY-XMS
SUN 670
64 kbauds
CIRCE

54 kbauds
RouterRouterEtherNet lOMbits/sec

50 Desktop Computers

Printers

IBM 3090

EtherNet 10Mbits/sec

Terminals

6 Workstations

1992
Nuclear Data Requests by Subject Category
Total number is 967

Bibliographic Data

36.9%

Nuclear Structure Data
26.7%

Graphs and Documents
3.6%

Experimental Data
13.4%
Evaluated Data
19.4%

Nuclear Data Requests by Requester Category

Total number is 967

Governmental Labs.
64.1%

Private Companies
3.0%International Org.

3.8%

Universities
29.1%

Number of Online users
400
300 2 0 0 ••100 -u. 1 1 1 1

0 dec-1987

dec-1989
dec-1991
dec-1993
dec-1994
dec-1988
dec-1990
dec-1992
feb-1994
dec-1995

1993 usage by service
TextualE-requests
Abstracts J
Tdb .!
Nudat J
Ensdf
Nsr
Eva-Jet
Cinda
Exfor
0

200

400

600

800

R3

IAEA Nuclear Data Section
PROGRESS REPORT
April 1994

I.

Staff

Since the last NRDC Meeting held in Obninsk in October 1991, Josef Schmidt retired
as head of the Nuclear Data Section after more than twenty years in that position. The
position was unfilled for more than one year until Charles Dunford arrived in July 1993.
Douglas Muir, the Section's Deputy Head has returned to Los Alamos National Laboratory.
After a vacancy of about one year, Pavel Oblozinsky from the Slovak Academy of Sciences,
Bratislava, Slovakia was hired to fill that position. During this period, first Valentin Konshin
and then Hans Lemmel served as acting Section Head. At the beginning of 1994, Wang
Dahai from PR China retired. He had been handling many of the Technical Cooperation
projects assigned to NDS. His post will not be filled.
During the next two year period, S. Ganesan will be leaving the Section at the endof his five year appointment and Nikolai Kocherov will be retiring. Neither position will befilled due to the Section's budget being reduced by about 15% in the 1995-1996 period.
Sometime in 1995, it is planned to shift one post from the Atomic and Molecular Unit into
nuclear data to complete the implementation of the budget reduction. As a result of thesecuts, the Section's nuclear data processing activity will be terminated and the nuclear dataassessment activity reduced.
Budgeting and planning have been complicated by the failure of IAEA Member States
to pay their assessment on time. As a result, each year 10-12% of the Section's program has
been deferred. When the deferred money is released at unforseen times, deferred activities
have to be carried out on short notice. Sometimes priorities have changed. At the present
time NDS is spending deferred program money from 1992 and 1993.

n.

CINDA

After a period of thorough testing of the CINDA programs, we have loaded the NDS
CINDA master file from the IBM onto the VAX in December 1993. Rejected entries havebeen corrected and transmitted to other centres. As of January 1994, all NDS CINDA
operations go through our VAX.
Also, the whole CINDA book (i.e. text pages plus entries) will be produced from theVAX. This again requires substantial changes in the book production programs, and we may
have to envisage delays in the schedule. This change is the second within a short period; thefirst change was needed to adapt the book production programs to a new Laser printer.
CINDA 92 was published as a supplement to CINDA 91. However, CINDA 93 wasand CINDA 94 will be published again in the form of a cumulative issue.

-2-

HI.

EXFOR

We believe that the neutron data compilation in EXFOR is sufficiently complete forarea 3. A backlog that resulted from a vacant post in 1992, has been eliminated. Exfor
TRANS tapes have been sent to the other centers in our normal rate of 5 tapes per year.
Since the last NRDC meeting, September 1992, 83 EXFOR entries have been
compiled and 157 revised, containing totalling 393 new data-sets.
Due to the changeover from the IBM to the VAX computer, EXFOR check programs
have not been updated for several years.
The dictionaries were updated regularly (latest dictionary transmission: TRANS 9067,
April 1994). Among the more important items were codes for the new countries in East
Europe as well as a number of new codes and/or expansions for renamed journals.

IV.

Evaluated Data
The following evaluated data libraries have been produced by NDS in the reporting

period:-Update of the International Reactor Dosimetry File IRDF;
JONACS (joint neutron activation cross-sections), a comprehensive data libraryfor 11 000 neutron activation reactions with 636 target nuclides in the incident
neutron energy range up to 20 MeV; (this was produced for fusion applications("FENDL/A") but is, of course, also useful for other applications);
FENDL (evaluated nuclear data library for fusion applications), a processed
neutron reaction data library including materials selected from available generalpurpose libraries available in pointwise and processed form.

The recent release of JEF-2.2 is gratefully acknowledged. For the other 4 main
evaluated data libraries updates and additional sublibraries have been received. All werechecked and documented in the IAEA-NDS-... documentation series. A new comprehensive
index IAEA-NDS-107 has been issued.
NDS staff worked mainly on the nuclear data libraries for the FENDL project. This
work is not only essential for fusion neutronics calculations but also for fission reactor andother applications. A most important by-product of this work was the code validation doneby S. Ganesan which led to a number of improvements in the NJOY code system.

V.

VAX Computer and On-line Data Service

Significant progress has been made on the migration of the NDS computing activity
to its VAX computer. Deferred equipment money from 1992 was used to purchase computer-3terminals for all the staff members. This includes 5 X-window terminals for the mostintensive computer users. The disk storage has been increased by 2 gigabytes to 7 gigabytes
and the last memory doubled to 64 megabytes, the maximum allowed on the MicroVax 4000
system. A 4mm audio-digital data tape unit was added for backup purposes and large scaledata transmission to users with compatible units. Two HP-LaserJet Printers with augmented
paper trays have been installed to handle the increased output from the VAX. The present
computer configuration is attached.
We have also installed new software. With the installation of the MULTINETTCP/IP software we are now able to access the INTERNET directly instead of through a
DEC UNIX gateway. File transmission difficulties were resolved and user access to theon-line service simplified. We have also purchased DISKKEEPER software to manage ourdisk usage and FLINT for Fortran source code checking.
Our current priority is to discontinue use of the IAEA IBM mainframe for ourcenter's work by the end of 1994. The use of NNDC database software has helped us
immensely. Our major remaining tasks are related to migrate administrative programs.
The on-line data service is identical to the NNDC system. Very close cooperation
between NNDC and NDS is maintained so that problems are solved expeditiously and newfeatures introduced while continuing to use identical software. In the past nine months, theNDS service has added access to a number of computer codes for processing ENDF andENSDF formatted data files. Significant improvements in the video version of the userinterface have also been made. Multiple file transmission within a single SEND commandusing a new multiple-selection menu is now possible. The NSR data base program allows
a wildcard search of retrievable parameter values which significantly enhances the power ofthe program. Complete data libraries can be downloaded from the service. Currently
available are the IRDF files and the 1993 Audi-Wapstra mass evaluations.
The NDS on-line data service is now beginning to show steadily increasing usage.
The direct link to INTERNET, advertising of the service and the growing access to electronic
computer networks within our service area account for the growth. In 1993, 590 retrievals
were performed by NDS on-line service customers; already in the first four months of 1994,
866 retrievals have been made.

VI.

Request Statistics

Due to staff fluctuations the definition of requests and subrequests has varied slightly.
The present practice is:a request is an incoming letter (or telephone call);if this letter requests documents and evaluated data and EXFOR data, then thisis three subrequests;
if a subrequest contains requests for, e.g. the entire JEF library and one specificthreshold reaction from IRDF, then this is two detailed subrequests.

-4-

Attached is a statistical table for subrequests and detailed subrequests in 1993.
The total figure of 559 subrequests is low compared to figures between 600 and 800
in the past years. This can be attributed to normal fluctuations which much depend on therelease of important data libraries; and also to vacant posts in 1992/1993 which were thereason why there was no Nuclear Data Newsletter issued between Sept. 1992 and Nov. 1993.
The Newsletter is the main connection between the data center and its customers.
Attached is also the list of 81 countries that have requested nuclear data informationin the period 1989 to 1992. Few additional countries should be added to this list since then.
The on-line service is gradually expanding. As shown on the attached table we havenow 127 users on 113 active accounts, from 31 countries. The main users (with more than
6 users) are not only from the neighbourhood (Austria, Czechia, Poland, Hungary) but also
from remote countries like Australia, Brazil, Israel, South Korea.

VIL

Meetings
The detailed meeting and consultant schedule for 1994 is attached.
In 1995 the NDS will organize the following meetings:
1)
2)
3)
4)
5)
6)
7)

International Nuclear Data Committee Meeting
NRDC Technical Consultants Meeting
FENDL-2 Development Advisory Group Meeting
2nd Photon Production Research Coordination Meeting
Final Long-Lived Activation Cross Sections Research Coordination Meeting
Reactor Decommissioning Data Advisory Group MeetingFirst Charged-Particle Nuclear Data Research Coordination Meeting

In 1996 the NDS will organize the following meetings:
1)
2)
3)
4)
5)
6)
7)
8)

Nuclear Reaction Data Centres Advisory Group Meeting
Nuclear Structure and Decay Data Advisory Group Meeting
2nd Nuclear Model Parameters Research Coordination Meeting
FENDL-2 Processing Advisory Group Meeting
Final Fission Product Yield Research Coordination Meeting
INDC Nuclear Standards Data File Consultants' MeetingFirst Charged Particle Fusion Reaction Research Coordination Meeting
Workshop on Nuclear Data for Applications in Nuclear Technology

VIII. Publicationsa)Data center services
The main printed materials supporting the data center services are the Newsletter andthe IAEA-NDS-... documents.

-5The IAEA Nuclear Data Newsletter is published once a year advertising theavailability of new or updated data libraries and printed materials such as neutron data
related meeting proceedings, INDC reports, data processing codes, and others.
Originally, this Newsletter was distributed primarily to scientists in the NDS service
area ("area 3"). But meanwhile we have received numerous requests from scientists
in all areas to be put on the distribution list primarily for INDC reports or certain
rare data libraries which are distributed not by all of the service centers. Therefore,
the distribution is now worldwide, however still with emphasis on area 3. The
Newsletter now presents the addresses of all nuclear data service centers. (Total
distribution: 4000, about 'A in area 3 and xh outside area 3.)
IAEA-NDS-documents are not reports in the normal sense. They are sent out only
together with data libraries; no data library is sent out without an IAEA-NDSdocument containing at least brief information on contents, format and origin of thedata library.
Special issues are:
IAEA-NDS-0:
IAEA-NDS-7:
IAEA-NDS-107:
IAEA-NDS-150:b)index to the IAEA-NDS-documents
index to the available nuclear data libraries
joint index to BROND, CENDL, JEF, JENDL, and
ENDF/B, IRDF
User's Manual of the NNDC/NDS Online Nuclear Data
Service

INDC reports and others
INDC reports continue to be published and distributed. They are either NDS
produced or submitted by member states or national and international institutes. They
may contain nuclear data information of the following categories:
progress reports by countries or institutes;
original scientific work of interest;
minutes and proceedings of meetings;
work by participants of co-ordinated research projects;
translations of Russian (and other) originals.
A list of recent INDC reports is attached. It contains about 50 reports per year witha distribution between 50 and 500.

IAEA Nuclear Data Section
PROGRESS REPORT
April 1994

ATTACHMENTSV.

VAX Computer and On-line Data Service-

VI.

Request Statistics-

VII.

Subrequests 1993
Country Statistics 1989 - 1992
On-line service users by country

Meetings-

VIII.

IAEA configuration

NDS Meetings 1994

Publications-

INDC report index end 1992 - March 1994

IAEA Configuration
NDS/WS - Central VAX - LANOTRQETHERNETDELNI

DECserverOOO
E1A42316x

ETHERNET
DEMPR

8x

ETHERNET
DEMPR

8x^,1-J,

Oihmw Kern

(G urillfl)

VxT-2000
PC's with ETHERNET Adaptor(13 units)

T1
Cabling
Systemfrom IAEA
max. 100m

LN06R

8x

VAXstation
3100/38
16MB

HP4M(2 units)<

ETHERNETDELNIETHERNET
DEMPR

VAXsystem
4000-20064MB

DEMS8-SXSNA Gateway

DECsystem
5100-RISC
16MB

DEMSB-FX
X,25 Router

MVS/ESATCP/IP

Modem
RemoteDiagnosis

PublicX.25
Network
DATEX-P

Existing
Token
Ring

PC's invarious
Areas

using
DK3fTAL

IBM-HOST

University of Vienna
INTERNET

TCP/IPSubrequests 1993
MONTH

MINOR
Codes

FREQUENCY |B1t>1 1o
I Data

lEval
IData

DOC' S

[4

Expt
Data

TOTAL
•

JANUARYFEBRUARY
MARCH
APRIL
MAY

JUNE
JULY
AUGUST

I
I
I
I

0

I
I

0

I
I

0

SEPTEMBEROCTOBERNOVEMBER
DECEMBER

I
I
I

TOTAL

I
38 I
32

4

0

4

0

22

6

0 |

5
1

27

I

13

0

2

I
16 I
29 I
16 I
17 I
17 I

0

73

292

3

0

2

0 |

13

7 I

26

13

0

22

•

I
23 I
16

1

0

19

40

29

0

I

3

1
1 1
4 1
0 1
1 1
2 1
4 1
2 1
2 1
1 1
0 1
0 1

0

18

0

1

14

5

22 |
30
6
5
183

51
•

0

62
•

0

54
•

0

58
-

0

80
-

32

0
-

0

38
•

0

26

0

55
-

0

60
-

0

26
V

0

e

24
566

Detailed Subrequests 1993
MONTH

MINOR

FREQUENCY

B1b"MoData

Codes

I Doc's

I

Eva!
Data

4

Expt
Data

I
TOTAL

JANUARY

0

5 |

85

26

1

FEBRUARY

0

8 |

102

37

1

MARCH

0

8 |

90 |

31

4

APRIL

30

0

0I
0I
0I
0I
0I

117
148
133

0

7 |

78

MAY

0

38 |

101

39

1

JUNE

0

1 |

27

31

2

oI

61

JULY

0

2 |

39 |

11

6

0

4 |

59

8

2

0I
0I

58

AUGUSTSEPTEMBER

0

3 |

106

26

2

137

OCTOBER

0

15 |

33

31

oI
oI

NOVEMBER

0

4 |

37

8

0 I

0 |

49

0

5 I

37

9

0

oI

51

DECEMBER

1

100

TOTAL

119
6
367

794

287

h

magnetic tapes
cartidges
diskettes

have been used in 1993 for request answering. (Georgina).
(Tapes and diskettes for center-to-center data exchange not counted.)

+

115
179

73
80

1201

Table D.5.C.: REQUESTS 1989 - 1992
COUNTRY STATISTICS
COUNTRY
India
China
USA
Soviet Union
HungaryJapan
Germany
BrazilPolandCzechoslovakia
Romania
Argentina
Austria
United Kingdom
German Dem. Rep.
Egypt
Yugoslavia
Pakistan
Korea
Algeria
Bulgaria
South Africa
Indonesia
Iran
Italy
VietnamIsraelCuba
ThailandBangladesh
FranceMexicoSaudi Arabia
Australia
Belgium
Nigeria
Libya
Malaysia
CanadaTaiwanNetherlands
Burma
Albania
MoroccoSweden
Peru
Zaire
Kenya
Switzerland
TurkeyFinland
Sri Lanka
ZambiaIraq
Venezuela
Bolivia
Philippines
Russia
Spain
Syria
Ghana
Portugal
Sudan
Chile
Denmark
Uruguay
EcuadorJordanNew Zealand
Costa Rica
CyprusIvory Coast
KuwaitMadagascar
NorwaySenegalSwaziland
Tunisia
UgandaUnited Arab Emirates
Zimbabwe

TOTAL

BIBL.

CODES

DOCUM.

EVAL.

EXPT.

309
270
205
173
143
131
128
121
116
108
87
60
57
57
56
54
53
50
40
39
36
36
35
35
34
32
31
28
27
25
25
25
25
24
24
24
23
22
20
19
16
17
14
14
14
13
12
11
11
11
9
9
9
8
8
7
7
6
5
5
4
4
4
3
3
3
2
2
2
1
1
1
1
1
1
1
1
1
1
1
1

0
3
1
1
1
0
0
1
0
0
0
0
1
1
0
0
0
2
0
0
0
0
1
0
0
1
0
0
0
0
0
0
0
1
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0

28
20
10
16
13
1
2
12
14
7
7
10
2
2
3
7
8
9
7
2
3
2
1
1
1
3
1
7
3
4
1
3
5
1
0
3
1
2
1
4
0
1
2
1
1
0
2
1
1
0
3
1
2
1
2
0
1
1
0
0
0
0
0
0
0

196
166
148
72
84
115
97
66
71
62
56
35
29
46
41
33
30
27
26
26
20
22
23
22
28
15
20
8
16
13
21
13
15
9
23
16
14
17
19
9
9
13
8
8
12
6
10
9
4
9
3

76
51
44
75
37
15
29
40
27
34
23
14
11
7
12
13
14
7
7
9
11
12
8
11
5
13
10
9
8
7
3
9
5
13
1
5
8
3
0
6
7
3
4
2
1
7
0
1
5
1
3

9
30
2
9
8
0
0
2
4
5
1
1
14
1
0
1
1
5
0
2
2
0
2
1
0
0
0
4
0
1
0
0
0
0
0
0
0
0
0
0
0
0
0
3
0
0
0
0
1
1
0
2
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0

0
0
0
0
0
0
0
0
0
0
0
0

81 countries served between 1989 and 1992

1

5
5
4
7

5
3

1
2
0

5
4
2
2
3
3
3
1

0
0
0
0
1
0
0
0
0
0
0
0
0
0
0

2
0
2
0

7

1
2
2
1
0
0
1

2
2
0
1

0

1
1
1
1
1
1
1
1
1
1

0
0
0
0
0
0
0
0
0
0

1
0
0
2

0

0

ONLINE SERVICE USERS BY COUNTRY
Country

Active Accounts

Argentina
Australia
Austria
BrazilCanadaChile
Croatia
Czech Republic
FranceGermany
Hungary
India
IsraelItaly
LatviaMexicoNetherlands
New Zealand
PolandRomania
RussiaSlovakia
South Africa
South Korea
Spain
Switzerland
TaiwanThailand
United Kingdom
U:S.A.

Venezuela

31
113
127

countries
active accounts
users

0
13
12
8
2
1
2
10
4
3
6
0
6
3
1
1
1
1
9
3
3
2
2
6
1
2
1
1
2
5
2

Users ("Names")

1
15
16
9
2
1
2
10
5
3
8
1
6
3
1
1
1
1
9
4
4
2
2
6
1
2
1
1
2
5
2

NDS MEETINGS 1994
Month/
Duration

Responsible
Officer

Type/Title of Meeting

Location

18-21

Pashchenko

SPM "Charged-Particle and Photonuclear Data
Evaluations for FENDL"

Smolenice,Slovakia

11/4 - 6/5

GanesanWorkshop on Nuclear Data Processing and Reactor
Physics Calculations for Applications in Nuclear
Technology

Trieste, Italy

25 -27

Lemmel/Schwerer

AGM "13th Nuclear Reaction Data Centres"

Paris, France

4-6

Oblozinsky

NEANSC Working Party on Evaluation
Cooperation

Oak Ridge, USA

9 - 13GanesanWorkshop on Nuclear Data Processing and Reactor
Physics Calculations for Applications in Nuclear
Technology

Bologna, Italy

April

May

Responsible
Officer

Type/Title of Meeting

Location

9 - 13

DunfordInternational Conference on Nuclear Data for Scienceand Technology

Gatlinburg,USA

16 -20

Lemmel/Dunford

Coordination of the Nuclear Structure and Decay
Data Evaluators Network

Berkeley, CA
USA

5 -6

Janev

TC "8th Meeting of the IFRC A+M Subcommittee"

Vienna7-9

Janev

AGM "Atomic, Molecular and Particle-Surface Interaction
Data for Divertor Physics Design Studies"

Vienna7-9

Pashchenko

SPM "Comparison of Activation Cross Section
Measurements and Experimental Techniques"

St. Petersburg,
Russia

1 2 - 16

Ganesan

AGM "Improved Evaluations and Integral Data
Testing for FENDL"

Garching,
Germany

19 - 23

Oblozinsky

RCM "Development of Reference Input Parameter Libraryfor Nuclear Model Calculations of Nuclear Data"

Ravenna, Italy

Month/
Duration
May (contd.)

September

Type/Title of Meeting

Location

Langley

RCM "Thermomechanical Properties of Plasma Facing
Materials"

Vienna4-7

Pashchenko

RCM "Establishment of an International
Reference Data Library of Nuclear Activation
Cross Sections" (1st RCM)

Debrecen,
Hungary

10- 12Janev

RCM "Radiative Cooling Rates of Fusion Plasma Impurities"

Vienna17-20

Lammer

RCM "Compilation and Evaluation of Fission
Yield Nuclear Data"

Vienna24-28

LemmelDevelopment of an International Chart of
the Nuclides

ViennaPashchenko

RCM "Improvement of Neutron-Induced He
Production Cross Sections" (2nd RCM)

Beijing,
China

Month/
Duration

Responsible
Officer

September (cont'd)

26-30

OctoberNovember

1 -4

Month/Duration

Responsible
Officer

Type/Title of Meeting

Location

7-11

Kocherov

CM "Nuclear Data for Fission Reactor
Decommissioning"

Vienna14 - 17

Oblozinsky

RCM "Measurement, Calculation and Evaluationof Photon Production Data"

Bologna,
Italy

PAGE
INOC DOCUMENT
DESIGNATORDATE OF
DISTR1B.

INDC(N0S)-264/G

SEP 92SUMMARY REPORT OF THE IAEA ADVISORY GROUP MEETING
ON "NUCLEAR DATA FOR NEUTRON MULTIPLICATION IN
FUSION-REACTOR FIRST-WALL AND BLANKET MATERIALS"
HOSTED BY THE CHINA SOUTHWEST INSTITUTE OF NUCLEAR
PHYSICS AND CHEMISTRY (SWINPC) AT CHENGDU, CHINA.
19-21 NOVMEBER 199O
PREPAREO BY D.W. MUIR AND A . B . PASHCHENKOIAEA NUCLEAR DATA SECTION. VIENNA, AUSTRIASEPTEMBER 1992
36 PAGES

INOC(CCP)-349/G

JAN 92NUCLEAR CONSTANTS NO. 1 (1992)(IN RUSSIAN)
S2 PAGESINDC(CPR)-O26/G

OCT 92

SEVERAL STUDIES ON MEDIUM ENERGY NUCLEAR DATACALCULATION AND EVALUATIONOING-BIAO SHEN
INSTITUTE OF ATOMIC ENERGY, BEIJING, CHINAOCTOBER 1992
22 PAGESINDCtNDS]-2S5/G

OCT 92TOTAL NEUTRON CROSS-SECT ION OF U-238 AS MEASURED
WITH FILTERED NEUTRONS OF 55 KEV AND 144 KEV
PHAM ZUY HEIN, ET. AL.
DALAT NUCLEAR RESEARCH INSTITUTE, DALAT, VIETNAM
OCTOBER 1992
S PAGESINDC(GER)-O35/L

APR 92

NEAN0C-3O7/U
KFK-5062

PROCEEDINGS OF A TOPICAL CONFERENCE ON NUCLEAR
DATA FOR FUSION REACTOR TECHNOLOGYKERNFORSCHUNGS2ENTRUM KARLSRUHE. FRG, 91-10-23
EDITED BY S. CIERJACKSAPRIL 1992
119 PAGESINDCfGERI-036/L

JUL 92

NEA/NSC/D0CI92IS
KFK-SO79

PROGRESS REPORT ON NUCLEAR DATA RESEARCH IN THE
FEDERAL REPUBLIC OF GERMANYFOR THE PERIOD APRIL 1, 1991 TO MARCH 3 1 , 1992
EDITED BY S. CIERJACKSKERNFORSCHUNGSZENTRUM KARLSRUHE. FRG
JULY 1992
78 PAGES

INOC(CCP)-34S/G

JUL 92

PHOTONUCLEAR DATA INDEX 19S6-1990
V.A. VARLAMOV, M . E . STEPANOV, V.V. SAPUNENKO
MOSCOW STATE UNIVERSITYINSTITUTE OF NUCLEAR PHYSICSCENTRE FOR PHOTONUCLEAR EXPERIMENTAL DATAJULY 1992
71 PAGES

INOCtJPN)-162/U

AUG 92PROGRESS REPORT (JULY 1991 TO JUNE 1992 INCLUSIVE)EDITOR S. KIKUCHI, JAPANESE NUCLEAR DATA COMMITTEEJAERIAUGUST 1991 '147 PAGES

IN0C(NDS)-263/G*SP

JUL 92

ACTIVATION CROSS SECTIONS FOR THE GENERATION OF
LONG-LIVED RADIONUCLIDES OF IMPORTANCE IN FUSION
REACTOR TECHNOLOGYTEXTS OF PAPERS PRESENTED AT THE FIRST MEETING
OF A CO-ORDINATED RESEARCH PROGRAMME ORGANIZED BY
THE IAEA AND HELD IN VIENNA, 11-12 NOVEMBER 1991
COMPILEO BY WANG DAHAt, IAEA NUCLEAR DATA SECTIONJULY 1992
1S9 PAGESINDCINDS)-271/G+NY

JAN 93

MASS DISTRIBUTION IN «.3 MEV NEUTRON-INDUCEDFISSION OF U-23S
LI' ZE, ET AT.
CHI'NA INSTITUTE OF ATOMIC ENERGY
P.O. BOX 27S, BEIJING, CHINAJANUARY 1993
12 PAGESINDC(CCP)-350/G

JUL 92NUCLEAR CONSTANTS NO. 2 (1992)
I IN RUSSIAN)
97 PAGESINDCINDS)-26S/G

JAN 93

SUMMARY REPORT OF THE IAEA CONSULTANTS' MEETING ON"CHARGEO-PARTICLE AND PHOTONUCLEAR DATA LIBRARIESFOR FENOL"HOSTED BY THE U.S. NATIONAL NUCLEAR DATA CENTERATTHE BROOKHAVEN NATIONAL LABORATORY, UPTON. U.S.A.
PREPAREO BY A.S. PASHCHENKO, IAEA, VIENNA, AUSTRIAJANUARY 1993
26 PAGESINDCINDS)-266/G

JAN 93

REFERENCE NUCLEAR PARAMETER LIBRARY FOR NUCLEAR
OATA COMPUTATIONSUMMARY REPORT OF A CONSULTANTS' MEETING ORGANIZEDBY THE IAEA AND HELD IN VIENNA, AUSTRIA.
13-15 NOVEMBER 1991
PREPARED BY G. REFFO, 0. BERSILLON, D.W. MUIR AND
A.B. PASHCHENKOJANUARY 1993
22 PAGESINDC(NOS)-269/L

JAN 93

NUCLEAR DATA REQUIREMENTS FOR FISSION REACTORDECOMMISSIONINGPROCEEDINGS OF THE ADVISORY GROUP MEETINGORGANISED BY THE IAEA
VIENNA, T-11 SEPTEMBER 1992
EDITED BY N.P. KOCHEROV, IAEA
JANUARY 1993
122 PAGESORIGINAL
DOCUMENT ID.

DOCUMENT TITLE, AUTHOR, OTHERIDENTIFICATION NUMBERS, ETC..

31

INDC DOCUMENT
DESIGNATORDATE OP
DISTRIS .

ORIGINAL
DOCUMENTID.

DOCUMENT TITLE, AUTHOR, OTHERIDENTIFICATION NUMBERS, ETC...

INOCCHOSI-2T3/E

SUMMARY REPORT OF THE FIRST IAEA RESEARCH
CO-ORDINATION MEETING ON "IMPROVEMENT OF
MEASUREMENTS, THEORETICAL COMPUTATIONS ANDEVALUATIONS OF NEUTRON INDUCEO HELIUM PRODUCTIONCROSS SECTIONS" HOSTED BY THE INSTITUTE OF
EXPERIMENTAL PHYSICS OF KOSSUTH LAJOS UNIVERSITY
AT DEBRECEN, HUNGARY, 17-19 NOVEMBER 1992
PREPARED BY A.B. PASHCHENKO. IAEA
MARCH 1993
2 1 PAGESINDC(CCP)-3S1/C

THE TALK PRESENTED AT INTERNATIONAL WORKSHOP"FUSION NEUTRONICS EXPERIMENTS (FRASCATI, ITALY,
21-22 SEPTEMBER 1992)
14 MEV FACILITY AND RESEARCH IN IPPE
S.P. SIMAKOV, ET. AL., INSTITUTE OF PHYSICS AND
POWER ENGINEERING, OBNINSK, RUSSIA
O.YU. CHUVILIN, ET. AL., INSTITUTE OF ATOMICENERGY, MOSCOW, RUSSIAJULY 1993
32 PAGESINDC(CCP)-352/G

NUCLEAR OATA FOR SCIENCE AND TECHNOLOGYFIVE PAPERS FROM U.S.S.R. AUTHORS
A.B. PASHCHENKO AND H.D. LEMMEL [EDITORS)JULY 1993
23 PAGESINDCISLK]-0O1/G

PEGAS, PRE-EOUILIBRIUM-EQUILIBRIUM GAMMA-ANO-SPIN
CODE IPC VERSION)
E. SETAK AND P. 08L0ZINSKY
INSTITUTE OF PHYSICS, SLOVAK ACADEMY OF SCIENCES,DUBRAVSKA CESTA 9, S422S BRATISLAVA, SLOVAK REP.
MARCH 1993
2t PAGESINDC(SEC)-1O1

NEANDC-311/U

INOCIBZL)-O3S/G

NUCLEAR DATA STANDARDS FOR NUCLEAR MEASUREMENTS
1991 NEANOC/INSC NUCLEAR STANDARDS FILEEDITOR H. CONDE, UPPSALA UNIVERSITY, UPPSALA,SWEDEN
131 PAGESl»92
A COMPARATIVE STUOY OF FEW-GROUP CROSS-SECTIONSFOR THERMAL REACTOR FUCL CELLSLUIZ ENRIQUE CLARO AND AIRTON PRATIMINISTRY OF AERONAUTICS
DEPARTMENT OF RESEARCH AND DEVELOPMENTINSTITUTE OF ADVANCED STUDIESSAO JOSE DOS CAMPOS, SP , BRAZH.
TRANSLATED BY THE IAEA
MARCH 1993
IS PAGESINDC(BZL)-O36/G

MAR

INOC(CPR)-O29/L

DEC 92

INDCIJPN1-1S4/GR

MAR

93

ACCURACY VERIFICATION FOR CALCULATION OF INVENTORYIN JPDR DUE TO NEUTRON ACTIVATIONTAKENORI SUKEGAWA, NOBUO SASAMOTO AND KAZUO FUJIKI
JAPAN ATOMIC ENERGY RESEARCH INSTITUTE
TOKAI-MURA, NAKA-GUN, rSARAKI-KEN. 319-11, JAPANMARCH 1993
38 PAGESINDC(NDS)-272/G+SP

MAR

93

CO-ORDINATED RESEARCH PROGRAMME ON MEASUREMENT AND
ANALYSIS FOR 14 MEV NEUTRON - INDUCEDDOUBLE-DIFFERENTIAL NEUTRON EMISSION CROSSSECTIONS NEEDED FOR FISSION AND FUSION REACTORTECHNOLOGYSUMMARY REPORT OF THE 3RD AND FINAL RCM ORGANIZEDBY THE IAEA ANO HELD AT CHIANG MAI, THAILAND.
31 MARCH-2 APRIL 92, PREPARED BY WANG DAHAI, IAEA
MARCH 1993
161 PAGESINDC(NDS)-2S1/SP

FEB 93

NUCLEAR OATA FOR NEUTRON MULTIPLICATION IN
FUSION-REACTOR FIRST-WALL AND BLANKET MATERIALSTEXTS OF PAPERS PRESENTED AT THE AGM
ORGANIZED BY THE IAEA IN COOPERATION WITH
SOUTHWEST INSTITUTE OF NUCLEAR PHYSICS AND
CHEMISTRY (SWINPC) AND HELD IN CHENGDU, CHINA,
19-21 NOVEMBER 1990COMPILED BY A.B. PASHCKENKO AND O.W. MUIR, IAEAFEBRUARY 199312« PAGESAPR 93

GRUKON - A PACKAGE OF APPLIED COMPUTERPROGRAMSSYSTEM INPUT ANO OPERATING PROCEDURES OFFUNCTIONAL MODULES
V.V. SINITSA AND A.A. RINEISKIJINSTITUTE OF PHYSICS AND POWER ENGINEERINGOBNINSK, THE RUSSIAN FEDERATION
TRANSLATED BY OR. A. LORENZ FOR THE IAEAAPRIL 1993
71 PAGESINDC1CCP)-344/G

L

93

ICAROG: A PROGRAM FOR CONVERSION OF A DATA LIBRARY
IN THE WIMSD/4 FORMAT FROM THE BCD TO THE BINARY
CODE AND VICE VERSAALEXANDRE D. CALOEIRAMINISTRY OF AERONAUTICS
INSTITUTE OF AOVANCED STUDIESSAO JOSE DOS CAMPOS, SP, BRAZIL
TRANSLATED BY THE IAEA
MARCH 1993
S PACESCNIC-OO7O6
CNDC-OOt1

COMMUNICATION OF NUCLEAR DATA PROGRESS
NO. < (1992)
CHINA NUCLEAR INFORMATION CENTER
CHINESE NUCLEAR OATA CENTERATOMIC ENERGY PRESS
BEIJINGDECEMBER 1992
79 PAGESPACEIHDC DOCUMENT
DESIGNATORDATE OF
DISTRIB.

ORIGINALOOCUMENTID.

DOCUMENT TITLE, AUTHOR, OTHeRIDENTIFICATION NUMBERS, ETC...

ACC.NOINDC(CCP)-3S3/G

LECTURES PRESENTED AT THE INTERREGIONAL TRAINING
COURSE ON APPLICATION OF NUCLEAR DATA ANO
MEASUREMENT TECHNIQUES IN NUCLEAR REACTOR ANDPERSONAL NEUTRON DOSIMETRYOBNINSK, THE RUSSIAN FEDERATION
15 JUNE TO 1O JULY 1992
APRIL 1993
5S PAGES

INOC(NDS)-277/SP

IAEA TECHNICAL COMMITTEE MEETING ON"ATOMIC AND MOLECULAR DATA FOR FUSION REACTORTECHNOLOGY"
12-16 OCTOBER 1992. CADARACHE, FRANCESUMMARY REPORTPREPARED BY R.K. JANEVMARCH 1993
7O PAGESINOCIARGJ-0I2/G

INTEGRAL ACTIVATION CROSS SECTION RATIOS OF
TI (N.XISC-46, TI (N.X1SC-47, TI•»»(N,P)SC-48,
TI-50(N,ALPHAICA-47 RELATIVE TO
A1-27(N,ALPHAINA-24 IN THE NEUTRON SPECTRUM
PRODUCED BY 23.2 MEV DEUTERONS INCIDENT ON A
BE METAL TARGET
M . D . BOVISIO DE RICABARRA, ET, AL.,
ARGETINE NATIONAL ATOMIC ENERGY COMMISSION
MAY 1993
7 PAGESINDCIIND)-O4S/S

INDCt JPN) -1 63/L

INOCINDJ)-279/G,

MAR

N

93

BARC/1993/E/005

PROGRESS REPORT ON NUCLEAR DATA ACTIVITIES IN
INDIA FOR THE PERIOD JULY 1990 TO JUNE 1992COMPILED BY P.D. KRISHNANITHEORETICAL PHYSICS DIVISIONBHABHA ATOMIC RESEARCH CENTRE, INDIA
1993
6S PAGESJAERI-M-93-O4C
NEA/NSC/D0C(93)2

PROCEEDINGS OF THE 1992 SYPMPOSIUM ON NUCLEARNOVEMBER 26-27, 1992, JEARI, TOKAI, JAPAN(EDS.) MAMORU BABA ANO TSUNEO NAKAGAWA
MARCH 1993
379 PAGESFEB 93DATA

REPORT ON THE CONSULTANTS' MEETING ON TECHNICALASPECTS OF THE CO-OPERATION OF NUCLEAR REACTIONOATA CENTERS
IAEA HEADQUARTERS, VIENNA, AUSTRIA
1-3 SEPTEMBER 1992
EDITED BY H.D. LEMMEL, 0. SCHWERER, H. WIENKEFEBRUARY 1993
»1 PAGESINDC(CCP)-3S4/G

EVALUATION OF EXCITATION FUNCTIONS FORLEVELS IN NEUTRON REACTIONS
O.T. GRUDZEVICH, ET. AL.
POWER PHYSICS INSTITUTEOBNINSK, RUSSIA
1991
20 PAGES

IN0C(CCP)-3S5/G

INELASTIC SCATTERING OF 1-2.5 MEV
23SU AND 23»U NUCLEI
N.V. KORNILOV, ET. AL.
POWER PHYSICS INSTITUTEOBNINSK, RUSSIA
1991
22 PACES

IN0C(CCP)-3S6/G

SELF-CONSISTENT DESCRIPTION OF ISOMER YIELDS IN
NEUTRON REACTIONS
O.T. GRUDZEVICH, ET. AL.
INSTITUTE OF PHYSICS AND POWER ENGINEERINGOBNINSK, RUSSIA
1993
2O PAGESINDCICCP)-357/G

NEUTRON REACTIONS WITH NUCLEI IN ISOMERIC STATES
O.T. GRUDZEVICH, ET. AL.
INSTITUTE OF PHYSICS ANO POWER ENGINEERINGOBNINSK, RUSSIA
1993
1 I PAGESINDC(CPft)-O3O/1

ISOMERIC

NEUTRONS BY

CNIC-00750
CNDC-0012

COMMUNICATION OF NUCLEAR DATA PROGRESSNO. 9 I 1993)
CHINA NUCLEAR INFORMATION CENTER
CHINESE NUCLEAR DATA CENTERATOMIC ENERGY PRESS
BEIJINGJUNE 1993
113 PAGESINDCIJPN)-165/U

JUN

93

JAERI-M-93-124

MEASUREMENT OF FORMATION CROSS SECTIONS OFSHORT-LIVED NUCLEI BY 14 MEV NEUTRONS - RU,
CD, SNYOSHIMI KASUGAI, ET. AL .
JAPAN ATOMIC ENERGY RESEARCH INSTITUTE
JUNE 1993
41 PAGESIN0CIUSAJ-1OS/L

MAY

92

BNL-NCS-47947
D0E/NDC-S9
NEANDC(US)-230

REPORTS TO THE DOE NUCLEAR DATA COMMITTEECOMPILED BY THE' NATIONAL NUCLEAR DATA CENTER
U.S. DEPARTMENT OF ENERGY, NUCLEAR DATA COMMITTEE
MAY 1992
113 PAGESINDC(CCP)-35S/G

JUL 93

NUCLEAR CONSTANTS NO. 3-4(IN RUSSIAN)
122 PAGES(1992)

33

1 920

PAGE
INDC DOCUMENT
DESIGNATORDATE OF
DISTRIB.

ORIGINAL
DOCUMENT 10.

DOCUMENT TITLE. AUTHOR, OTHERIDENTIFICATION NUMBERS, ETC...

INOCIGER]-037/LN

JUL 93

NEA/NSC/D0C(93)17
JUEL-2SO3PROGRESS REPORT ON NUCLEAR DATA RESEARCH IN THE
PEOERAL REPUBLIC OF GERMANY FOR THE PERIODAPRIL 1, 1992 TO MARCH 31, 1993
EDITED BY S.M. QAIM. FORSCHUNGSZENTRUM JUELICH,
INSTITUT FUER NUKLEARCHEMIE, JUELICH, GERMANY
JULY 1993
46 PAGESINDC(GER)-O3S/G

JUN

93

ANALYTIC NUMBER THEORY AND THE NUCLEAR
DENSITY
A. ANZALDO MENESES
JUNE 1993
131 PAGESINDC(NOS)-2SS/G

AUG

93

COMPARISON OF THE EVALUATIONS OF THE
CROSS SECTIONS FOR THE NEUTRON DOSIMETRY
REACTIONS 197AU(N,2N] 196AU, S9C0(N,2N)5SC0
93NB(N,2N)92MNBJOSE MARTINEZ-RICO
AUGUST 1993
14 PAGESACC.NOLEVELANOINDCINDSI-2S2/G

SEP 93

STANDARD INPUT DATA SETS FOR NUCLEAR MOOELCOMPUTATIONS OF NUCLEAR DATASUMMARY REPORT OF THE IAEA CONSULTANTS' MEETING
HOSTED BY THE CENTRO DI CALCOLO OEL E.N.E.A.,
BOLOGNA, ITALY AND HELD AT SIROLO (ANCONA), ITALY.
FROM 21 TO 25 JUNE 1993
A . 8 . PASHCHENKO, ET. AL.
SEPTEMBER 1993
IS PAGESINDC(CCP)-3S9/G

NOV 93

PREPARATION OF EVALUATED DATA FOR A FISSIONBARRIER PARAMETER LIBRARY FOR ISOTOPES WITH
Z - S2-9S, WITH CONSIDERATION OF THE LEVELDENSITY MOOELS USED
G.N. SMIRENKININSTITUTE OF PHYSICS ANO POWER ENGINEERINGOBNINSK. KALUGA REGION, RUSSIA
TRANSLATED BY THE IAEANOVEMBER 1993
31 PAGES

INOC(CCP)-3S0/S

NOV 93

EVALUATION OF THE 46TI[N.IN]45TI AND
54PE(N,2N)53M»GPE REACTION CROSS SECTIONS FOR
NEUTRON DOSIMETRY IN FUSION FACILITIESA PAPER PRESENTED AT THE INTERNATIONAL WORKSHOPON NUCLEAR DATA FOR FUSION REACTOR TECHNOLOGY
DEL MAR, CALIFORNIA, USA, 3-6 MAY 1993
S.A. BADIKOV, A.V. IGNATYUK, K.I. 20L0TAREV,
A.B. PASHCHENKONOVEMBER 1193
23 PAGESINDC1EUR1-027/G

JUN

93

INDCtJPN)-16S/U

AUG

93

INDClJPN)-167/L

OCT 93

INDC(NDS)-2S6/L

NOV

93

ACTIVATION CROSS SECTIONS FOR THE GENERATION
OF LONG-LIVED RAD IONUCLIDES OF IMPORTANCE IN
FUSION REACTOR TECHNOLOGYTEXTS OF PAPERS PRESENTED AT THE SECOND RESEARCH
CO-ORDINATION MEETING ORGANIZED BY THE IAEA IN
CO-OPERATION WITH TSI RESEARCH AND WESTINGHOUSE
HANFORD COMPANY ANO HELO IN DEL MAR, CALIFORNIA,
USA, 29-30 APRIL 1993, COMPILED BY A.B. PASHCHENKONOVEMBER 1993
155 PAGESINDC(NDS)-2»«/L

NOV

93

ACTIVATION CROSS SECTIONS FOR THE GENERATION OF
LONG-LIVED RAD IONUCLIOES OF IMPORTANCE IN FUSION
REACTOR TECHNOLOGYSUMMARY REPORT OF THE SECOND IAEA RESEARCH
COORDINATED MEETING HOSTED BY TSI RESEARCH,
DEL MAR, CALIFORNIA, USA, 29-30 APRIL 1993
EDITED BY A.B. PASHCHENKO, IAEANOVEMBER 1993
24 PAGESINDCIPAKI-OOS/LNOV 93

THE GLOBAL OPTICAL POTENTIALS AND NEUTRON-NUCLEUS
SCATTERING DATA
I.E. OURESHI AND O.H. KHANRADIATION PHYSICS OIVISION, PINSTECH, P.O. NILORE,ISLAMABAO. PAKISTANNOVEMBER 1993
13 PAGES

INOCtSWDI-OI4/L»P

NOV 93

ABSOLUTE GAMMA BRANCHING RATIOS FOR FISSION
PRODUCTS IN THE MASS RANGE 74-165
G. RUDSTAMTHE STUDSVIK NEUTRON RESEARCH LABORATORY
S-611S2 NYKOEPING, SWEDENNOVEMBER 1993
63 PAGES

NEA/NSC/00CI93)11

ANNUAL PROGRESS REPORT ON NUCLEAR DATA 1992
CENTRAL BUREAU FOR NUCLEAR MEASUREMENTSGEEL [BELGIUM)
JUNE 1993
SO PAGESPROGRESS REPORT (JULY 1992 TO JUNE 1993
EDITOR Y. NAKAJIMA
JAPANESE NUCLEAR DATA COMMITTEEJAPAN ATOMIC ENERGY RESEARCH INSTITUTE
AUGUST 19939« PAGESJAERI-M-93-195

BIBLIOGRAPHIC INDEX TO PHOTONUCLEAR
DATA (19SS-1992)
TETSUO ASAMI AND TSUNEO NAKAGAWAOCTOBER 1993
200 PAGES34

INCLUSIVE)

REACTION

1934

PAGE
INOC DOCUMENT
DESIGNATORDATE OF
DISTRIB.

ORIGINALOOCUMENT 10.

DOCUMENT TITLE. AUTHOR, OTHERIDENTIFICATION NUMBERS, ETC...

INDCt BLR)-OO1/L

EVALUATED NEUTRON DATA FOR URANIUM-233
L.A. BAKHANOVIC, ET . AL .
NUCLEAR POWER INSTITUTE, MINSKTRANSLATED BV DR. A. LORENZ FOR THE IAEA FROMRUSSIAN PREPRINT IYAEH-2<251 [1992)
DECEMBER 1993
74 PAGESINDC(NDS)-267

ATOMIC COLLISION OATABASE FOR LI BEAM
INTERACTION WITH FUSION PLASMAS
R.K. JANEV, J.J. SMITH, IAEA, VIENNA, AUSTRIA
F. AUMAVR, ET. AL . , TECHNISCHE UN IVERSITAET,VIENNA, AUSTRIAJ. SCHWEINZER, MAX-PLANCK INSTITUT F. PLASMAPHYSIK, GARCHING, GERMANYDECEMBER 1993
87 PAGES

IN0C[NDS)-29O/G+CW

OEC 93

UPDATE OF THE WIMS-D4 NUCLEAR DATA LIBRARYSTATUS REPORT OF THE IAEA WIMS LIBRARY UPDATEPROJECTCOMPILED BY S, GANESANDECEMBER 1993
1S8 PAGES

INOCtSEC)-104/U+G

WRENDA 93/94
WORLO REQUEST LIST FOR NUCLEAR DATACOMPILED AND EDITED BY N. KOCHEROV AND
P.K. MCLAUGHLIN, IAEA, VIENNA, AUSTRIA
PUBLISHED ON BEHALF OF NNDC, BROOKHAVEN, USA;
NEA DATA BANK, SACLAY, FRANCE; NUCLEAR DATASECTION, VIENNA, AUSTRIA: NUCLEAR DATA CENTER,
OBNINSK, RUSSIADECEMBER 1993
136 PAGESINDC(SEC)•IO5/U+S

REQUESTS FOR FISSION YIELD MEASUREMENTS
A SUPPLEMENT TO WRENDA 93/94 (PUBLISHED AS
INDCISEO-104)
ISSUED BY PARTICIPANTS OF THE IAEA CO-OROINATEDRESEARCH PROGRAMME ON THE COMPILATION AND
EVALUATION OF FISSION YIELD NUCLEAR DATACOMPILED AND EDITED BY M. IAMMER, IAEA, VIENNAFEBRUARY 1994
24 PACES

INDC(ARG)-011/G

NUCLEAR DATA IN ARGENTINA (1992-19931
PREPARED BY G.H. RICABARRA
COMISION NACIONAL DE ENERGIA ATOMIC*BUENOS AIRES. ARGENTINAMARCH 1993
9 PAGESINDC(CCP)-3S1/L

SELECTION OF RADIATION SOURCES FOR CALIBRATIONOF GAMMA-RAY SPECTROMETERS
F.E. CHUKREEV
I.V. KURCHATOV INSTITUTE OF ATOMIC ENERGY
MOSCOW, RUSSIAJANUARY 1994
9 PAGESIN0C(NDS)-2«O/SREPORT OF THE IAEA NUCLEAR OATA SECTION TO THE
INTERNATIONAL NUCLEAR DATA COMMITTEEJULY 199O - DECEMBER 1992
R. JANEV, N. KOCHEROV. H.D. LEMMEL (EOITORS)FEBRUARY 1993
«6 PAGESINDC(BUL)-014/L

AVERAGE GROUP DATA FOR 241PU IN THE 0.1-21.5 KEV
ENERGY REGION
N.T. KOYUMDZHIEVA AND N.B. YANEVANUCLEAR RESEARCH AND POWER INSTITUTE, SOFIA,BULGARIA[TRANSLATED FROM A RUSSIAN ORIGINAL PUBLISHED IN
YADERNYE KONSTANTY 4/1990)
TRANSLATION EDITOR: DR. ALEX LORENZFEBRUARY 1994
15 PAGESINDC(CCP)-362/L+N

ANALYSIS OF EXISTING DATA AND SPECIFICATION OF AN
EXPERIMENT TO DETERMINE THE 252CF HALF-LIFE TO THE
REQUIRED DEGREE OF ACCURACY
I.A. KHARITONOV(TRANSLATED FROM A RUSSIAN ORIGINAL PUBLISHED IN
YADERNYE KONSTANTY 4/1987)
TRANSLATION EDITOR: OR. ALEX LORENZFEBRUARY 1994
15 PAGESIHDC(CCP)-3C3/L+N

IDENTIFICATION OF HIGH-SPIN STATES IN 235U
V.E. MAKARENKO, F.E. CHUKREEV(TRANSLATION FROM A RUSSIAN ORIGINAL PUBLISHED IN
JADERNYE KDNSTANTY 4/19«3)
TRANSLATION EDITOR: DR. A. LORENZFEBRUARY 1994
11 PAGES

IN0C(CCP)-364/G

SELECTED PAPERS ON NUCLEAR DATA ANALYSIS(TRANSLATION OF RUSSIAN PAPERS PUBLISHED IN
YADERNVE KONSTANTY 1/19S9)
TRANSLATION EDITOR: OR. A. LORENZFEBRUARY 1994
3S PAGES

INOC(CCP)-3«S/L

MEASUREMENTS OF NEUTRON NUCLEAR DATA OF ACTINIDES[TRANSLATION OF SELECTED RUSSIAN PAPERS PUBLISHEDIN YADCRNYE KONSTANTY 19S7-1991)
TRANSLATION EDITOR: OR. A. LORENZFEBRUARY 1994
37 PAGES

33

ACC.NO

19*7

PAGE
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DESIGNATORDATE OF
DISTRIB.

ORIGINAL
DOCUMENTID.

DOCUMENT TITLE, AUTHOR. OTHERIDENTIFICATION NUMBERS, ETC...

INOCICCPI-366/L

EVALUATION OF NEUTRON NUCLEAR OATA OF ACTINIDES(TRANSLATIONS OF SELECTED RUSSIAN PAPERS PUBLISHEDIN VADERNVE KONSTANTV 1987-1991)
TRANSLATION EDITOR; DR. A. LORENZFEBRUARY (994
66 PAGESINDC(CCP)-367/L

INTEGRAL TESTS OF NEUTRON NUCLEAR DATA OF
ACTINIOES(TRANSLATIONS OF SELECTED RUSSIAN PAPERS PUBLISHEDIN VADERNYE KONSTANTY 19S7-1991)
TANSLATION SO I TOR: DR. A. LORENZFEBRUARY (99492 PAGESINDCtCCPJ-36S/L

ABSOLUTE MEASUREMENT OF THE CHROMIUM NEUTRONCAPTURE CROSS-SECTION IN THE 1 KEY TO 20 KEV
ENERGY RANGE
M.A. VOSKANYAN, ET. AL., I.V. KURCHATOV INSTITUTEFOR NUCLEAR ENERGY, MOSCOW
B.V. ZHURAVLEV, L.E. KAZAKOV, INSTITUTE OF PHYSICSAND POWER ENGINEERING, OBNINSK(TRANSLATED FROM A RUSSIAN ORIGINAL PUBLISHED IN
YADERNYE KONSTANTY 4/(991) TRANSL. ED.: A. LORENZFEBRUARY 1994, 6 PAGES

INDC(CCP)-369/L

SECONDARY NEUTRON EMISSION SPECTRA FROM SPHERICAL
AND HEMISPHERICAL SAMPLES OF MATERIALS OBTAINED AT
14 MEV NEUTRON ENERGY
A . I . SAUKOV, B.I. SUKHANOV, A.M. RYABININ
ALL-UNION SCIENTIFIC RESEARCH INSTITUTE OFENGINEERING PHYSICS, CHELYABINSK, RUSSIA[TRANSLATED FROM A RUSSIAN ORIGINAL PUBLISHED IN
YADERNYE KONSTANTY 4/1991)
TRANSLATION EDITOR: DR. A. LORENZFEBRUARY 1994, 27 PAGES

INDC(NDS)-296/G,ND

CO-ORDINATION OF THE INTERNATIONAL NETWORK OF
NUCLEAR STRUCTURE ANO DECAY OATA EVALUATIONSUMMARY REPORT OF AN IAEA ADVISORY GROUP MEETING
HOSTED BY THE CEC CENTRAL BUREAU FOR NUCLEAR
MEASUREMENTS IN GEEL, BELGIUM, 9-13 NOVEMBER 1992
EDITED BY H.D. LEMMELOECEMBER 1993
17 PAGESINDC(NOSI-30O/L

REPORT ON THE SECOND INTERNATIONAL ACTIVATIONCALCULATION BENCHMARK COMPARISON STUDY
E.T. CHENG, TSI RESEARCH, INC., SOLANA BEACH, USA
R.A. FORREST, CULHAM LABORATORY, CULHAM, UK
A.B. PASHCHENKO, IAEA NUCLEAR OATA SECTION, VIENNAFEBRUARY 1994
23 PAGESINDC[N0S)-299/L+P+

PREPARATION OF PROCESSED NUCLEAR DATA LIBRARIESFOR THERMAL, FAST AND FUSION RESEARCH AND POWER
REACTOR APPLICATIONSSUMMARY REPORT OF THE IAEA CONSULTANTS'S MEETINGORGANIZED BY THE IAEA AND HELD AT THE IAEA
HEADQUARTERS, VIENNA, AUSTRIA, 8-10 DECEMBER 1993
PREPARED BY S. GANESAN, IAEA NUCLEAR DATA SECTIONMARCH 1994
18 PAGESINDC(N0S)-297/L»F

REVIEW OF UNCERTAINTY FILES AND IMPROVED
MULTIGROUP CROSS SECTION FILES FOR FENOLSUMMARY REPORT OF THE IAEA ADVISORY GROUP MEETINGORGANIZED BY THE IAEA IN COOPERATION WITH JAERIHELD AT THE TOKAI RESEARCH ESTABLISHMENT. JAERI,
JAPAN, S-12 NOVEMBER 1993
PREPARED BY S. GANESAN, IAEA, NUCLEAR DATA SECTIONMARCH 1994
39 PAGESINDC(NDS)-29S/L+F

PREPARATION OF FUSION BENCHMARKS IN ELECTRONICFORMAT FOR NUCLEAR DATA VALIDATION STUDIESSUMMARY REPORT OF THE IAEA CONSULTANTS' MEETINGORGANIZED BY THE IAEA AND HELD AT THE IAEA
HEADQUARTERS, VIENNA, AUSTRIA, 13-16 DECEMBER 1993
PREPARED BY S. GANESAN, IAEA. NUCLEAR DATA SECTIONMARCH 1994
19 PAGESIN0CINDS1-3O3/E

STATUS OF IMPORTANT NUCLEAR OATA REQUIRED FOR ITERA PAPER PRESENTED AT THE INTERNATIONAL WORKSHOP ON
NUCLEAR DATA FOR FUSION REACTOR TECHNOLOGY
DEL MAR, CALIFORNIA, USA, 3-6 MAY (993
S. GANESAN, N. KOCHEROV, A. PASHCHENKO,
J.J. SCHMIOT, AND H. VONACH
MARCH 1994
174 PAGESINDC(NDS)-304/6.P

PROGRESS IN FISSION PRODUCT NUCLEAR DATAINFORMATION ABOUT ACTIVITIES AND REQUIREMENTS
IN THEFIELD OF MEASUREMENTS AND COMPILATIONS/EVALUATIONS OF FISSION PRODUCT NUCLEAR OATA (FPNO)NO . 14COLLECTED BY M. LAMMER. IAEA, NUCLEAR DATA SECTION
1994
119 PAGESINDCICPR1-031/L

CNIC-00S10
CNDC-0013

COMMUNICATION OF NUCLEAR DATA PROGRESS
NO. 1O (1993)
CHINA NUCLEAR INFORMATION CENTER
CHINESE NUCLEAR DATA CENTERATOMIC ENERGY PRESS
BEIJINGDECEMBER (993
150 PAGES36

ACC.NO

1 960

R4
THE CJD PROGRESS REPORT.
V.N.Manokhin
CINDA. 510 entries from the works published in 1992-1993 werecompiled. A total number of lines is 1839.
EXFOR. The compiling intolevel. During 1992-1993 TRANS

EXFOR

is

continued

4086-4094

ona steady

with 193 entries {71 new

and 122 corrected) were transmitted. A total numberof subentries

is 1723,from which 696 are new.
EVALUATED DATA.The CJD

evaluation

l.The systematics of (n,2n) anddeveloped.

Many(n,2n)

reactionsactivity

is as follows:(n,3n) cross sections wereneededfor

dosimetryandactivation were evaluated using the systematics.
2.The Russian Dosimetry File(RDF-94) was formed.It
46 react ions, f-rom which 36 ones were evaluatedcontains

in the CJD. At thepresent time the File is in process of checking and testing.
hat
nat
93
3. TheBROND-2

werefiles ofZr andcorrected

and

its isotopes,

improved

for

Sn,

FENDL

Nb

from

project.

A

cooperation of the CJD and Dr. R.McFarlaine helped very much tofind misunderstanding

in format presentation of data andprocessthese files by NJOY-91.
4. The CJD and CNDC have compared the data files for Cr, Fe
and

Ni

from

BROND-2and

CENDL-2.

The

reasonsofavailable

discrepancies are under study.
5. The evaluation of neutron data of Zn isotopes was madefor

BROND-2 library. The data were written in ENDF-6 format.
6. The work on adding new data photo-neutron

data

library

BOFOD is in progress.
7. The gas production library is created. The evaluated crosssections for separate isotopes will be included.
COMPUTER MATTERS. New computer system ALPHA APX 3600S with
OPEN VMS 1.5 and VAX DBMS 4.3

is installedin the CJD. A local

network on the base of this system and several PC 486 DX will becreated. It is supposed to adopt the NNDC online system.

R5
Chinese Nuclear Data Center (CNDC)
Status Report
Zhang Jingshang
Zhuang Youxiang

Zhao Zhixiang
Liang Qichang

1. General Situation
The major event at the CNDC in 1992 has been the accomplishment of CENDL-2.0 (Chinese Evaluated Nuclear Data Library,versin 2.0).
A new working station of SUN-10 with 64 MB main memories,
1.05 GB system memories and 2*2.0 GB disks has been put into
operation at the velocity of 90 mips. Three sets of PC mode
486 have been supplemented at CNDC.
On the basis of the researches on nuclear reaction theory,
a complete set of model code system for nuclear data calculation has been set up. It includes the codes UNF series and
MUP series as well as RCA, CCOM and DWUCK, in which DWUCK is
introduced from abroad.
Chinese Evaluated Nuclear Parameter Library (CENPL) has
been preliminarily established. The CENPL contains six sublibraries and has been provided for Chinese users. They are
as follows:(1) Atomic messes and characteristic constants for nuclear
ground states (CENPL-MCC);(2) Discrete level schemes and branch ratios of gamma
decay (CENPL-DLD);(3) Level density parameters (CENPL-LDL);(4) Giant dipole resonance parameters for gamma ray
strength functions (CENPL-GDR);(5) Fission barrier parameters (CENPL-FBP);(6) Optical model parameters (CENPL-OMP).
This project is supported by the IAEA.
2. Future work, manpower and priorities
Future work
The advanced CENDL-2.1 based on CENDL-2.0 will be accomplished in 1995. Much improvements will be made in four principal aspects:

(1) to supplement and update evaluations of some nuclides;(2) to do re-evaluations for some nuclides;(3) to add some files (for example, photon production dataand covariance matrix) to evaluations of some nuclides;(4) to make international comparison of evaluated nuclear
data, discover problems and solve them.
Staff
There are 18 senior scientists at CNDC. They are engaged
in various work:
Nuclear theory 4;
Neutron data evaluation 5;
Charged particle and photonuclear data
Nuclear structure and decay data 1;
Fission product yield 1;
Atomic and molecular data 1;
Parameter library 1;
EXFOR, CINDA, Data format 1;
Data service, Library management 1;
Group constant generating 1;
Benchmark testing 1.

1;

Priorities
Due to the requirement of the international exchanges
and financial limit, CNDC would like to enhance the cooperations on neutron, charged particle and photonuclear datawith other centers.
This is a top priority for CNDC.

R6

Status Report of JAERI/NDC and JNDC
Yasuyuki KIKUCHI
Nuclear Data Center,
Japan Atomic Energy Research Institute,
Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan

1. JAERI/NDC Activity
Nuclear Data Center of Japan Atomic Energy Research Institute (JAERI/NDC) plays
a role of national nuclear data center in Japan besides research activities. Its resent activities
are reviewed.
The most important activity is the evaluation and compilation of Japanese EvaluatedNuclear Data Library (JENDL) in cooperation with Japanese Nuclear Data Committee(JNDC). The revision 2 of JENDL-3 General Purpose File will be released soon as JENDL3.2. The evaluation is going on for various JENDL Special Purpose Files such as JENDLHigh Energy File, JENDL Fusion File, Minor Actinoid File, Covariance File, Activation Cross
Section File, Dosimetry File, PKA Spectrum File, (a,n) Reaction Data File, Photo Reaction
Data File.
Integrated Nuclear Data Evaluation System (INDES) is being developed, in order tokeep experiences accumulated in JENDL-3, to store basic data of nuclear physics used for
the JENDL-3 evaluation, and to support new evaluations. Roughly classified, INDES
functions are of three categories; to select the most suitable set of theoretical calculation codes
by applying knowledge engineering technology, to retrieve basic data described above, andto set up input data of theoretical calculation codes automatically.
Recently data needs for the high energy nuclear data increase. A code to calculate thecross section up to a few GeV is being developed on the basis of the quantum molecular
dynamics in cooperation with a group in the Advanced Science Research Center in JAERI.
The nuclear structure and decay data are evaluated under the international network of
ENSDF. Japan is in charge of the mass numbers from 118 to 129.
JAERI/NDC has experimental activities by itself and collaborating with universities
and laboratories in Japan. Measurements of nuclear data, such as activation cross sections
and double differential alpha-particle emission spectrum for neutron induced reactions ofstructural materials, and cross sections and double differential particle emission spectra forcharged particle induced reactions were performed.
Atomic and molecular data for fusion reactor applications are also evaluated andcompiled in international format by JAERI/NDC.
One of JAERI/NDC functions as the national center is collection and service of
databases for experimental and evaluated nuclear data. As to the experimental database, theretrieval systems of NESTOR2 for neutron incident reactions, and of CHESTOR for charged
particles and gamma-ray incident reactions have been developed. The international
collaborations and data exchange are made basically through JAERI/NDC. JAERI/NDC also
serves as the secretariat of JNDC.

2. JNDC Activity
Japanese Nuclear Data Committee (JNDC) has about 150 members in Atomic Energy
Society of Japan and JAERI. JNDC consists of three subcommittees, which are on nuclear
data, on reactor constants and on fuel cycle, six standing groups, steering and counselingcommittees. JAERI/NDC serves as the secretariat. The schematic diagram is attached.
Recent activities on the subcommittees and standing groups of JNDC are reported below.
2.1 Subcommittee on Nuclear Data
Subcommittee on nuclear data has 11 working groups (WGs).
(1) High Energy Nuclear Data Evaluation WG
Methods of the intermediate nuclear data evaluation are discussed and the evaluation
work for JENDL High Energy File is mainly performed by this WG. Actual work is
separated into two energy region of up to 50 MeV and of up to a few GeV. Comparison ofseveral theoretical codes was done for this work.
(2) Covariance Data Evaluation WG
This WG was organized to evaluate error data for JENDL. Different evaluation
methods of covariance matrices proposed by Japan, the United States and Europe werecompared and it was concluded to adopt Japanese method, which evaluates them fromphysical parameters of calculations.
(3) Evaluation and Calculation System WG
Integrated Nuclear Data Evaluation System (ENDES) is under development withknowledge engineering technology. INDES keeps data and experience of JENDL-3
evaluation work and economize the evaluation in future. Two temperature Madland-Nix
model was developed to calculate fission neutron spectra.
(4) Fission Product Nuclear Data WG
The evaluations and benchmark tests for JENDL-3 FP Data File were done by thisWG. The revision works for JENDL-3.2 were also performed.
(5) Activation-Cross-Section Data WG
The preliminary version of JENDL Activation Cross Section File was produced andbenchmark testing is now planned.
(6) PKA Spectrum WG
ESPERANT code, which creates the PKA/KERMA file from the evaluated nuclear
data file, was developed. This WG will also evaluate the intermediate energy neutron nuclear
data up to 50 MeV for lighter nuclei.
(7) Charged Particle Nuclear Data WG
The data related (a,n) and fusion reactions were researched. The experimental dataof thick target neutron and proton yields for proton and alpha-particle induced reactions on
several elements were collected and stored in EXFOR format.
(8) Photo-Reaction Data WG
The photo reaction data were evaluated at the incident gamma-ray energy up to 140
MeV for 31 nuclei as a phase I evaluation.
(9) WG on Revision of JENDL-3 Neutron Data
The revision work for JENDL-3.2 was performed except for the y-ray production
data.
(10) WG on Revision of JENDL-3 Gamma-ray Production Data
The problems of JENDL-3.1 about gamma-ray data were made clear and reevaluation for the important nuclei such as Fe and Ni was done.

2.2 Subcommittee on Reactor Constants(1) Fission Reactor Integral Test WG
The benchmark tests for the thermal and fast reactors were performed with the various
group constants and calculating codes.
(2) Shielding Integral Test WG
Various shielding benchmark tests were performed and its final report (JAERI-1330)
is under printing. The benchmark test for secondary gamma-ray is in progress. The researchof group constants and benchmark tests for intermediate energy nuclear data related to theaccelerator applications has been started.
(3) Dosimetry Integral Test WG
The JENDL Dosimetry File was produced and JAERI-1325 was published.
(4) Fusion Neutronics Integral Test WG
The benchmark tests related to the fusion neutronics are being performed.
(5) Standard Group Constants WG
The system of the standard group constants, which is called JSSTDL and consists ofneutron and gamma-ray cross sections made from JENDL-3, was improved. The utility
codes were developed.
2 3 Subcommittee on Fuel Cycle(1) Decay Heat Evaluation WG
The JNDC Decay Data Library has been finished. In order to expand the functions,the preliminary research work for spectrum calculation of beta-ray heating and calculationof delayed neutrons were performed.
(2) WG on Evaluation of Nuclide Generation and Depletion
The isotope yield data of spent fuel were collected and published as JAERI-M 9 3 061. The data book, JAERI-1324, on neutron yields and its spectra caused by (a,n) reaction
and spontaneous fission was published.
2.4 Standing Groups(1) JENDL Compilation GroupThe compilation works for JENDL general and special purpose files are performed.
(2) CINDA GroupThe bibliographic data of neutron nuclear data published in Japan are collected andsent to NEA Data Bank.
(3) WRENDA GroupThe experimental request data of Japan are collected and sent to IAEA.
(4) ENSDF GroupThe evaluations of nuclear structure data for nuclei whose mass numbers are from 118
to 129 are performed. The data except for mass numbers of 120 and 124 have been revised
until 1992.
(5) Group on Atomic, Molecular and Nuclear Data for Medical Use
This is newly re-organized group in 1993. Data needs from medical use are surveyed.
(6) Editorial Group of "Nuclear Data News"
This group publishes three issues of "Nuclear Data News" in Japanese in a year.

Japanese Nuclear Data Committee

Japanese Nuclear Data Committee——(May 1994)

JAERI / Nuclear Data Center

Steering Committee
Counseling Committee

JENDL Compilation GroupCINDA GroupWRENDA Group
ENSDF Group
Group on A&H Data and Nucler Datafor Medical Use
Editorial Group of"Nuclear Data News"

Subcommittee on Nuclear Data
High Energy Nuclear Data Evaluation HG
Covariance Data Evaluation IG
Fission Product Nuclear Data WG
Evaluation and Calculation System WG
Activation-Cross-Section Data WG
PKA Spectrum WG
Charged Particle Nuclear Data WG
Photo-reaction Data ffG
WG on Revision of JENDL-3 Neutron Data
WG on Revision of Gamma-ray Production Data
Subcommittee on Reactor Constants————

Fission Reactor Integral Test IG
Shielding Integral Test WG
Dosimetry Integral Test WG
Standard Group Constants WG

Subcommittee on Nuclear Fuel Cycle
Decay Heat Evaluation WG
WG on Evaluation of Nuclide Generation and Depletion
WG : forking GroupR7
Japan Charged-Particle Nuclear Reaction Data Group
Hajime TANAKA
Chairman of the Executive Committee
Status Report to the Advisory Group Meetingon the Co-ordination of the Nuclear Reaction Data Centres
From 25 to 27 April 1994
1. Characteristics of NRDF and specific applications
At first, we will give some characteristics of the NRDF database and the activity of theJapan Charged-Particle Nuclear Reaction Data Group (JCPRG). This database is intended
to dedicate not only for a technical usage but also for academic usage. The data compilingformat of NRDF is designed to compile various kind of data types which increase with theadvancement of research work of this field.
The scope of the objects to be compiled in NRDF is not limited to that of one or someparticular current applications. It includes all physical quantities measured in one experimentpublished. For example, NRDF contains recent data of high-energy beam and unstable-nuclei
beam experiments more than ordinary angular distribution or cross section data. Therefore
the scope of data compiling objects seems wider than EXFOR.
For a specific application, a certain corresponding retrieval system deals with the NRDF
database. The NRDF database may be used by various applications with their own retrieval
systems. The translation into the EXFOR system is one of such applications of the NRDF
database. The Index Database, which will be mentioned later, is another such application.
Therefore an application oriented usage will be dealt with a certain retrieval system of the
NRDF database. We are compiling all physical quantities of CPND with the NRDF format
for the reason.
The activity of JCPRG is supported by the Ministry of Education. In this point, JCPRG
differs from other two activities of Japan, which are supported by the Ministry of Scienceand Technology. The NRDF database is also approved by the Society of Nuclear Physics
including experimental and theoretical physicists in Japan.
Japan Charged-Particle Nuclear Reaction Data Group places four duties upon itself:(1) Compiling all CPND produced in Japan with NRDF;(2) Translating data in NRDF into EXFOR format;(3) Making a combined index database for the CPND in both of NRDF and(4) EXFOR for the convenience of the customers in Japan;(5) Distributing CPND and Promoting utilization within Japan.
2. Organization and members of JCPRGThe JCPRG is organized by two committees and secretariat in order to accomplish above
four duties.
Advisory committee:
Yoshinori AKAISHI (Institute for Nuclear Study, Tokyo Univ.)
Yasuhisa ABE (Research Institute for Fundamental Physics,
Kyoto Univ.)Hidetugu IKEGAMI (Research Center for Nuclear Physics, Osaka Univ.)
Hajime OHNUMA (Tokyo Institute of Technology)
Hikonojo ORIHARA (Cyclotron and Radioisotope Center, Tohoku Univ.)
Mituji KAWAI (Kyushu Univ.)
Yasuyuki KIKUCHI (Japan Atomic Energy Research Institute)
Teijiro SAITHO (Tohoku Univ.)
Fumihiko SAKATA (Institute for Nuclear Study, Tokyo Univ.)
Khoji NAKAI (National Institute for High Energy Physics)
Akira HASHIZUME (Institute of Physical and Chemical Research)
Hiroshi YOSHIDA (Tokyo Institute of Technology)
Executive committee:
Hajime TANAKA (Chairman, Sapporo-Gakuin Univ.)
Kiyoshi KATO (Vice-Chairman, Hokkaido Univ.)
Akira OHNISHI(Hokkaido Univ.)
Shigeto OKABE (Hokkaido Univ.)
Toshiyuki KATAYAMA(Hokusei-Gakuen Univ.)
Hiroyasu NAGATA (Hirosaki Univ.)
Hiroshi NOTO (Hokusei-Gakuen Univ.)
Masaki CHIBA (Sapporo-Gakuin Univ.)
Secretariat:
Hitomi YOSHIDA
Office address:
Department of Physics
Hokkaido Univ.
Kita-10 Nishi-8, Kita-ku
Sapporo, 060
Tel: +81-11-706-2684
Fax: +81-11-746-5444
E-mail: yoshida@nucl.phys.hokudai.ac.jp
Working Staff:
Data compiling:
Hirokazu TEZUKA(Tohyo Univ.)
Takahisa KOIKE(Hokkaido Univ.)
Yuka A0KI(Tohoku Univ.)
Yasushi NARA(Hokkaido Univ.)
NRDF System Maintenance:
Shigeo MUKAI(Hokkaido Univ.)Chiba who is a member of the executive committee has a responsibility for translating
NRDF data into the EXFOR format, and keeping EXFOR data received and user servicing.
Katayama who is also a member of the executive committee is now investigating possibilities
and methodology for evaluation of CPND.
3. Recent progress(1) Compiling CPND produced in Japan
We have been compiling CPND produced in Japan with the NRDF format since 1987
constantly. In 1992 and 1993, we have newly added 65 and 55 entries in the NRDF library
respectively. These newly added entries are the ones that were all produced by accelerators inJapan. Main institutes are Tohoku univ., Tsukuba univ., KEK, JAERI, RIKEN, INS, TokyoIns. Tech., RCNP and Kyushu univ.. Almost all CPND produced from these institutes havebeen stored in NRDF. By March 1994, amount of the data compiled have reached more than
1200 entries (1258) about 57 MB.
(2) EXFOR translation
In 1992 we submitted to NDS TRANS E010. It contains 29 entries, which were converted
out from the NRDF library compiled in 1991. In March 1994 we submitted TRANS E011.
The TRANS E011 contains 26 entries. These entries were converted out from the NRDF
library compiled in 1992. Now, these two TRANS are requested error corrections.
As mentioned above, the NRDF database is including many kind of data, therefore it is
not possible to translate all of NRDF data into the EXFOR format. We have been translating
only the parts of NRDF data which can be translated.
(3) Index information system of CPND
We have developed a retrieval system for the index information of CPND and installed
it in Hokkaido University Computing Center. The ORION Information Retrieval System is
employed for the installation. The purpose of this retrieval system is to open the way forthe researchers in Japan to get benefits from utilizing the Charged-Particle Nuclear Reaction
Data which are complied and stored in both of NRDF and EXFOR libraries.
The received CPND in the EXFOR format from IAEA have been accumulated to theamount of 30 MB, consisting of about 1500 entries. It may be a part of our responsibility to
prepare an access path of utilizing the data as a valuable resource for the research activities
in Japan.
So, the index information retrieval system was developed to find EXFOR entries or subentries having specified features. This installation is a trial version to the system on NACSIS-IR(Information Retrieval service of the National Center for Science Information System). In
the near future, the system developed will be available on NACSIS-IR in order to be of use
to all potential researchers in Japan.
(4) Customer service
We are realizing that Customer services should be emphasized. Our activities have beenreported by "NRDF ANNUAL REPORT" to almost all nuclear physicists and some nuclear
engineers in Japan since 1988. Each one contains regular reports such as NRDF data compiling, the EXFOR translation and other relating matters, and some topics which may direct
our activities in advance.
Picking up some topics from the recent reports, compilation of hypernuclear data is discussed in "NRDF ANNUAL REPORT 91", "Production of nuclear experimental data" and"proton induced reaction data in NRDF" are surveyed in the 92 Report so as to perform
evaluation.
4. Computer Facility
We utilize the Hokkaido University Computing Center for the storage and retrieval of
NRDF and EXFOR information. The Hokkaido University Computing Center installs with

Hitachi M-880H and S-820/80 computers. These computers are running by MVS or UNIXcompatible operating systems.1 They are also connected to the National Academic Information Network. Thereforeresearchers of the universities or institutes in Japan can access our
NRDF or EXFOR information through the Network.
There are personal-computers or workstations available at our own laboratory or office.
They are also connected to a local and the National Academic Information Network. We areable to communicate with each other and others overseas through computer networks.
5. Future of activities
Major tasks that we have a responsibility to do are compiling and storing CPND produced
in Japan, and supplying with data service to home users through international data exchange.
The activity and organization of JPCRG is based on Nuclear Research Laboratory, Department of Physics, Hokkaido University, which is supported with the regular working budget
and administered by the Ministry of Education and Hokkaido University. The organizationof JPCRG has got acknowledgment of the Nuclear Research Community in Japan. We arealso getting supports from many researches. Therefore our activity will be going forward
steadily. We are making effort to perform the matters in hand mensioned below.
(1) CPND Compiling
We estimate the amount of data produced in Japan per year to be about 3 MB. Althoughalmost all CPND produced ever year in Japan are compiled, it is not yet complete. Especially,
recent data of unstable nuclear beems at RIKEN and of high-energy experiments at KEK
should completely be stored in NRDF.
(2) EXFOR translation
We are now translating only the parts of the NRDF data which can be translated. The
EXFOR translation will be continued in this way. As NRDF contains various kind of physicalquantities, we will try to increase parts which can be translated into the EXFOR.
(3) Information system of CPND
The current version of the Index Information system include only EXFOR index information. We are also planning to add NRDF index information to this system. The NACSIS-IR
is currently not able to accept other than index database. We are intending to install CPND
customer service on NACSIS-IR in future when NACSIS will also be able to accept numerical
databases.
(4) Customer service
We are developing a new service through National Center for Science Information Systems(NCSIS): Index Information Retrieval System for CPND in both NRDF and EXFOR formats.
(5) Others
We are studying CPND in NRDF in several aspects for evaluation:
1) What physical quantities really exist?;
2) In the case of choosing Total-Cross-Section, is it feasible to evaluate?, are there sufficient
data or energy range?;3) As NRDF data includes also optical potential, ares there any data evaluation model,
simulation method or code?
We are also planning to make an evaluation system of the nucleosynthesis by using very
low-energy data in NRDF.
a

IP Address: "133.50.16.16"; Domain Address: "osf.cc.hokudai.ac.jp"

R8

STATUS REPORT OF THE RIKEN NUCLEAR DATA GROUP
toThe IAEA Advisory Group Meeting
On the Coordination of the Nuclear Reaction Data Centers
Paris, 25 - 27 April 1994

Y. Tendow
EXFOR
We continue to collect and compile the production cross section data forthe 20 medical isotopes as well as some other extended varieties of isotopes.
We had collected over 70 works not included in the EXFOR, and started in
the compilation of them. We have transmitted the trans R008 (and its
revision R009) to NDS, which includes 11 works, 56 subentries with 63
excitation functions.
(d, x) reactions
35 (curves)
3( He, x) reactions 19(a, x) reactions
7(p, x) reactions
2

ENSDF
We continue the mass-chain evaluation as a member of the Japanese
ENSDF working group. Re-evaluation or update for A = 129 mass chain
has been completed and is in author post-review at the moment. Update
evaluation for A = 120 mass chain is now in progress coming to acompletion before long.
NSR
NSR file compilation for secondary sources (annual reports) of Japaneseorigin published in 1993 has completed and transmitted to NNDC.
RIKEN Ace. Prog. Rep.
41 (reports)
JAERI TV Annual Rep.
18
OULNS Annual Rep. (Osaka Univ.)
23
RCNP Annual Rep. (Osaka Univ.)
20
INS Annual Rep. (Tokyo Univ.)
14
UTTAC Annual Rep. (Univ. Tsukuba) 9
CYRIC Annual Rep. (Tohoku Univ.)
8
We are working on the compilation for 1994 secondary sources.

Computers
The central mainframe computer in RIKEN has been downsized from two
FACOM M1800 / 20, (256 MB main memories) to one FACOM M1800 / 10,(64 MB main memories) which is also supposed to be disused by the end of
this year. We are changing to a new system with a super computer andworkstation networks. Nuclear data group is using several PC's for primary
input and processing the data. Some of the PC's are as follows:
DECpc 466d2 MTE, 8MB memories, 525 MB HD,
NEC PC-9801, 7 MB, 120 MB HD,
IBM PS / 5530 (equivalent to PS / 2), 6MB, 40 MB HD,
Macintosh Ilci, 20 MB, 100 MB HD.
We also have a VAX network system (VAX-6610, VAX station 4000-60,
micro VAX II etc.) in the RIKEN Accelerator Facility area, linked to thecentral mainframe computer. At present we are not extensively using themfor data compilation works but we shall have to transfer to the VAX system
due to the upcoming disuse of the central mainframe computer.

Staff
There are no improvement in man-power condition since previous time.
The schedule of the continuous compilation jobs is rather tight for the staffof our scale. Efforts to simplify and routinize the compilation works as wellas to enhance man-power are being continued.
Regular member, proper
1 (EXFOR, ENSDF, NSR )Regular member, part-time
1 (computer)
Non-regular member, part-time 2 (EXFOR, ENSDF)
Non-regular member, assistant 1 (file and copy management)

CCP: Conununicuion control Ptoocisor
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16MB

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Fig. 1. Overview of the data acquisition system at the
RIKEN Ring Cyclotron.

R9
Charged Particle Reaction Data Compilation and Evaluation.
F.E.Chukreev
After our last Meeting (1991) we have prepared three TRANS
which contain integral cross sections for radioactive isotopes
production.
I would like to distinguish our compilation of
Levkovskij's book [1] as ENTRY A0510.
This ENTRY contains 542
Subentries.
We have been forced this big work, as we had wish to informscience community about the results of several years unpublishedinvestigations.
We have believed that low circulation and russian
language of this book does not promote for the knowledge of these
data.
After our meeting at Obninsk we prepared the code to
calculate alpha-particle induced neutron yield from homogeneousmixed elements. We have an experience to compare our calculations
with Chernobyl's data for neutron yield from melted materials andgood results have been observed.
We have plan to continue our compilations for medical
radioisotope production and integral data which are needed fortransmutation of radioactive wastes of nuclear power stations. Our
plan
includesthecompilations of some investigations forthermonuclear fusion which were not available at last time.
Besides we would like to decrease our contribution for"Pending EXFOR retransmissions" of Dr. 0. Schwerer. We have plan
to evaluate some data to monitor of He-3 beams.
CAJAD would like to use our meeting to discuss some problems
future compilations and use of its.
Why we compile experimental data?
Different groups have different answers on this question,
probably.
Our answer is:
1. To present science information as computer reading form.
2. To distinguish the major result and peculiarities ofexperiments without any "philosophy".
3. To conserve for science community the opinions of thescientists which used these data.
The execution for first item have notanyprincipal
hardnesses, although I can not say that all problems are decided.
The execution of second and third items has some hardnesses.
First, I would like to take your attention for item 2 . If
you have studied EXFOR entries attentively, you could see someeventswhen you do not understand of the subject of thisinvestigation.
There are some curious
thingsandobviousmisunderstanding by the compiler.
For example, CAJAD have missed a defect of a printing-officeand our checking code did not find this error. Our attention forthis error have been taken by Dr. 0. Schwerer and we thank Dr.
Schwerer.
But similar curious things are not "the privilege" of CAJAD
only.
These errors have been created by an inattention of thecompilers and senior physicists, which must check a compilation.
Now I would like to go over to third item. Active rules of
EXFOR are hindered to correct curious things and to conserve theopinions of another scientists.
Active rule:"Alterations to EXFOR entries are transmitted
only by the originating center and are included in the regular
EXFOR transmissions." forbids to include any changes in B-Library,which has been prepared by Prof. H. Munzel group. B-Library hasvery much deviation from active rules and these deviations makedifficult computer search in this library.
We have taken your attention by MEMO-A/65 for another cases
when the corrections are obligatory(!).
Who must do needed corrections?
Our Meeting must findanybody who could prepared a consideration on this subject.
Afterthis consideration will be created we must discuss it by usual MEMO
exchange and to accept new rule during to next Meeting. If we will
not do it, then big labor, which have been invested to create
EXFOR-Library, will be depreciated or be lost.
We understand that refuse from this rule must be accompanied
by check information "who, when, why" included this correction.
Else EXFOR users become involved.
I would repeat that the refusal from this rule is needed!
Checking codes and EXFOR Manual.
As I know, three checking codes have been created
1. by NNDC USA.
2. by NDS.
3. by CAJAD.
As
ourexperienceshow each checking code has somepeculiarities.
These peculiarities had been created by the difference ofcompilation objects and the wish to exclude the most frequenterrors.
During to last years we include in our checking code someessential changes to exclude founded bugs and to include additional
checks.
But we must say that our checking code find some errors which
could not be founded by NDS checking code and vica versa.
Is it bad or good? My opinion - this is good.
We are not convinced that checking code which will haveability for to exclude all errors is possible.
This opinion iscreated by differences for EXFOR rules interpretation.
I could advise NDS, which have responsibility for EXFORMANUAL, to increase the requirement for text formalist of EXFOR.
The number of the phrase as "...if one heading is to be defined,
the coded information may be omitted" must be decreased, because arequest for coded information will intensify compiler attention.
Compiler attention could be improved by using of the stencil.
The examples similar stencils could be found in CAJAD practice and
AMPEX code (V.Osorio, NDS).
CAJAD activity for CPND EXFOR coordination.
During to our last Meeting at Paris I had the request tocoordinate CPND EXFOR compilation.
I had believed that my colleges will give work for me very much.
But I have the requests a little. I intend that our CPND libraryhas some duplicated ENTRY and I hope to make special check on thissubject, when I shall have time for this control.
Reference[1]
V.N.Levkovsij, Activation cross section nuclei of average masses(A=40-100) by protons and alpha-particles with average energies(E=10-50 MeV).

RIO

The MSU INP CDFE Activities in
Photonuclear Data Compilation and Evaluationand in EXFOR, ENSDF, and NSR.
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, Russia
The CDFE Progress Report to the
12-th Consultants' Meeting of the Nuclear
Reaction Data Centres
25 - 27 April 1994 Paris

GENERAL
This report contains the review of the works carried out by he CDFE
after the Technical NRDC meting (Vienna, 1 - 3 September, 1992).
EXFOR
The production of the EXFOR files of experimental photonuclear
data remains the main direction of CDFE activity till now.
The work on correction of CDFE EXFOR TRANS MO 16 was
carried out in accordance with IAEA NDS (Dr. O.Schwerer) comments.
The result was processed in IAEA NDS as TRANS MO 17.
The new CDFE TRANS MO 18 was prepared. It includes the datafrom 19 papers have been published in various countries. This TRANS was
prepared on diskette as the supplement to this Progress Report.
The total number of CDFE-made MO-ENTRIES now is about 500(M0001-M0500 with several blanks). The CDFE photonuclear data
EXFOR fund includes also the last version of the total USA LLNL(Prof.B.L.Berman) EXFOR library (L0001-L0059) of photonuclear
reaction cross sections obtained using quasimonoenergetic photon beams
has been reprocessed in accordance with the new requirements of EXFOR
format for photonuclear data.
Additionally the CDFE has processed the almost complete total
photoneutron reaction cross section data library (EXFOR DATA sectionlike format) for nuclei from H-2 to Pu-239 based on the data have been
digitised earlier in the USA NIST (photonuclear data group of Prof.
E.G.Fuller) and presented to the CDFE for continuation of this kind ofphotonuclear data activity. Some of these data have been converted into
the real EXFOR format and included into CDFE MO 18 TRANS. This
work will be continued.

PHOTONUCLEAR DATA EVALUATION

Sticking the photonuclear data evaluation program and using themethod of reduction, independent on nuclear models, a priori information,
and any regularization as the tool for photonuclear reaction cross section
evaluation / I - 3 / the CDFE has analysed and evaluated the total
photoneutron reaction cross sections for the energy range of giant dipole
resonance (E = 10 - 50 MeV) for the number of nuclei (C-12, 0-16, Si28, Ca-40, Cu-63,65, Pr-141, Pb-208 etc.). Some of these data / 2 / havebeen processed as EXFOR ENTRY M0345 and other are now inprocessing.
Now the CDFE is working on the photonuclear data evaluation
program based on the Draft Proposals of Photonuclear Data Cooperation
Project between MSU INP CDFE and USA BNL NNDC withparticipation of scientists of USA LLNL /4/.
ENSDF
The CDFE has continued the activity in the field of using the otherinternational computer files, first of all the ENSDF, for both basic research/ 5 / and processing of requests of scientists, specialists, and experts first of
all from Russia universities and institutes for nuclear structure information.
The main field of activity in this direction was the work on
development of the new Personal Computer version of the relation nuclear
spectroscopy data base. The universal relation nuclear structure and decay
data base NESSY (New ENSDF Search SYstem) has been developed for
IBM/PC and compatible PC on the base of the ENSDF and the data basemanagement system (DBMS) PARADOX 3.5. The choice of the DBMS
PARADOX was determined by two principal factors. At first, this DBMS is
known to be quite fast for great data volumes (at present time the version
4.0 is declared to be the most fast in this class). At second, the PARADOX
has an advanced interface and a powerful query language named QBE(Query By Example).
The essence of the work carried out was that the ENSDF waschanged from its present eighty-column-card-image format to a tableformat that is needed for the DBMS PARADOX. To conserve the specific
ENSDF hierarchy the special key system was developed: all records of eachtable were numbered and assigned by "own" record key.
The NESSY gives to one the possibility for high efficiency processing(the search and retrieve of any kind physical data) of the information fromENSDF.
Because of very positive results of using of DBMS PARADOX for
the ENSDF information processing on IBM/PC the CDFE has carried out
the appropriate reorganisation of the EXFOR fund and began the similar
work for NSR.
Note added by NDS:
A related paper, "The Relation IBM/PC Nuclear Structure and Decay Data Base" by I.N. Boboshin,
V.V. Varlamov and S.K. Trukhanov, is being published as INDC(CCP)-370.

INFORMATIONAL ACTIVITY

Sticking the program of photonuclear data information publication
the CDFE continues the series of Photonuclear Data Bulletins and Indexes/ 6 / which contain the systematised information about the experimental
works on photo- and electronuclear reactions and inverse reactions ofradiative capture. Now the bulletins for 1991 - 1993 are in preparation.
COMPUTER FACILITY

Now the CDFE utilise the IBM/PC local network has been realisedon the base of 4 computers:
Computers: PC IBM AT/386DX-33
PC IBM AT/386DX-40
PC IBM AT/386SX-33
PC IBM XT/V20 -15
Network:

MHz-RAM 8 Mb-HDD 700 Mb;
MHz-RAM 5 Mb-HDD 170 Mb;
MHz-RAM 4 Mb-HDD 80 Mb;
MHz-RAM 640 kb-HDD 20 Mb.

Net Ware Lite; ETHERNET Adapters.

COMMUNICATION
To contact CDFE now one must use the following addresses:
MAIL:
TEL:
FAX:
TELEX:
E-MAIL:

119899 Moscow, Vorob'evy Gory, Moscow State University,
Institute of Nuclear Physics, CDFE(095) 939-3483(095) 939-0896
411483 M G U S U
VARLAMOV@COMPNET.MSU.SU

REQUEST SITUATION
Because of the strong changing of political and economical situationin the former SU the total number of requests decreased noticeably.
COOPERATIONThe CDFE is working in close cooperation with Russian Nuclear
Data Centres (CAJaD in Moscow and CJD in Obninsk). IAEA NDS.
USA BNL NNDC in the field of phoionuclear data compilation, and with
Nuclear Data Group of USA LLNL (the Draft Proposals of Photonuclear
Data Cooperation Project between MSU INP CDFE and USA BNL NDC
with participation of scientists of USA LLNL /4/) in the field of datacompilation and evaluation. In addition in 1991 an mutual understanding
about coordination of photonuclear data evaluation activity between the
CDFE and the JAERI (Japan) was achieved.
Unfortunately, the CDFE has no any financial support for theseworks absolutely and in hard financial situation of last years in Russia thisproduces a lot of obstacles for their normal continuation.
REFERENCES
1. N.G.Efimkin, V.V.Varlamov. "The Method of Reduction as photonuclear Data
Evaluation Tool". International Symposium on Nuclear Data Evaluation
Methodology". World Scientific. ISBN 981-02-1285-2. p. 585.
2. V.V.Varlamov, N.G.Efimkin, B.S.Ishkhanov, V.V.Sapunenko. The Evaluation of the
Photonuclear Reaction Cross Sections Using the Method of Reduction at Significant
Systematic Uncertainties. Voprosy Atomnoj Nauki i Tekhniki. Seriya: Yadernye
Konsranry. I (1993) >2
3. V.V.Varlamov. N.G.Efimkin. B.S.lshkhauov. Photonuclear Experiment Resolution
improvement and Intermediate Structure o\ the Giant Dipole Resonance. Proceedingof the 8-th Seminar on Electromagnetic Interactions of Nuclei at Low and Medium
Energies, 1NR. Moscow. 1992. p. 284.
4.

I.N.Boboshin. V.V.Varlamov. N.G.Efimkin, V.V.Sapunenko, M.E.Stepanov. CDFE
Progress Report - 1991. llth IAEA Consultants' Meeting of the Nuclear Reaction
Data Centres. Summary Repon. lNDC(NDS)-262. IAEA. Vienna. 1992. Annex 4.3.

5.

I.N.Boboshin. V.V.Varlamov. E.V.Nanova. Neutron Subshells of Ti. Cr, and Fe.
lzvestiya RAN. Seriya Fizicheskaya. 56 (1992) 93.

6. V.V.Varlamov. M.E.Stepanov. V.V.Sapunenko. Photonuclear Data Index 1986 1990. INDCiCCP)-348. IAEA. Vienna. 1992.

Rll

STATUS OF THE DEBRECEN NUCLEAR DATA GROUPIAEA Advisory Group Meeting on the
Co-ordination of the Nuclear Reaction Data Centers
Paris 1994

EXFOR

In 1992 installation of the PC version of the computer codes for EXFOR software(edition, retrieval) and for EXFOR based data evaluation (numerical format, plotting) havebeen started and the first experiences done. Unfortunately because of the complete failureof the computer used the programs and the files was lost, and work was started again fromthe beginning. After installing the software again the compilation of the absent datameasured by our group has been started as the first step .
We made EXFOR files using the ANDEX PC software. The software we have is anearly version of ANDEX 1.01, therefore some part of it does not work properly whichmake the work slow. Regarding, that this compilation work is the first for us the checkingof compiled file is in progress.
We have already compiled 15 sets of data file and other 10 are under compilation,
mainly data measured in Debrecen and Julich. The compiled data will be sent to The IAEA
till September 1994.

COMPILATION AND EVALUATION OF SELECTED REACTIONS
We have started and partly completed the compilation and the critical comparisonof several selected reactions used for production of medically important radioisotopes, formonitoring charged particle beams and for wear measurements. Compilation and evaluationof cross sections for production of 67Ga and '"In and p, d, alpha and 3He induced monitor
reactions on Cu, Ti, Ni and Fe are already published or to be published separately.
For data evaluation and for comparison of the measured cross sections with theory
installation of several model codes (STAPRE, EXIFON) are completed, and were used to
calculate excitation functions of Zn, Ar and Fe.

NEW CROSS SECTION DATA
Measurements of the cross sections for monitoring the beam performance foe isotope
production and for Thin Layer Activation technique have been continued, the aim of thestudies to complete the available data sets used in the most important applications and toclear the discrepancies arisen during evaluation of the data.

Monitor reactions
Measurement and data evaluation for proton induced reactions (have started earlier)on Ni and MtTi have been completed and published. Experimental investigation of proton
induced nuclear reactions have been started on an alloy containing Cr, Fe, Co, Mo and W
among other elements and on pure iron foils for monitoring of charged particle beams andfor application of thin layer activation technique. Irradiations have ben performed up to 18
MeV at the Debrecen MGC 20 cyclotron.
We have started our measurement to determine excitation functions of deuteroninduced reactions on chemically resistant materials, that is on natural Ni and Ti. The firstfew irradiations already have been done up to 14 MeV.
Experimental part of investigation of 3He and a induced nuclear reactions on natural
Ti and Cu for monitoring have been mostly completed. One part of the results has been
published. The data evaluation and critical comparison with earlier results are underdevelopment. The experimental results show that in few cases additional irradiations wereneeded for checking the reproducibility of the measurement, taking into account the very
contradicting results in the literature.
New experiments were done with a modified irradiation setup to measure theexcitation functions of alpha and 3He induced monitor reactions on natCu, natNi and natTi.
Data evaluation of the new measurements has been started.
nat

Reactions for isotope production
Excitation functions for production of the isotopes of 66Ga, 67Ga, i n In, 122I, 123I, ml,
75
Br, 77Br, 82Sr(82Rb), 82mRb, 81Rb(81Kr), 38K for medical use and 43K for ecological use havebeen measured.

Reaction for Thin Layer Activation technique
Excitation function of natFe(p,x)56Co nuclear reaction has been measured for
application in Thin Layer Application technique. Investigation of proton, deuteron and 3He
induced reactions on light elements (Be, B, C, N ...) has been started for production of 7Be
used in TLA.

NEW METHODS AND APPLICATIONS
The thin layer activation technique offers a basis for the routine study of very low
levels of wear and corrosion. Determination of the wear is based by measuring the activityof the collected wear debris or the residual activity in comparing it with the calibration
curve usually obtained experimentally. We have reproduced the calibration curve via
calculation using well measured evaluated excitation functions on Fe. The comparisons withthe measured calibration curves show that the excitation functions could be effectively used
for determination of the calibration curves.
Using gas targets it is important to check the shape of the beam and the density
distribution of the gas in the cells. To improve the applied methods for monitoring charged

particle beams during cross section and thick target yield measurement on gas targets an
optical method was applied for studying the beam broadening effect and the asymmetry of
the beam on horizontal and vertical beam lines. The first experiments show that expanded
beam shape can seriously influence the result of nuclear data measurement.
Additional experiments were done on vertical and horizontal beam lines to study thedependence of the pressure of the target gas, stopping power and range as a function of
bombarding beam intensities and time. The results were presented at Fifth International
Workshop on Targetry and Target Chemistry in Brookhaven, 1993.
For extended use of monitor reactions we decided to develop a computer code whichallows a more accurate determinations of effective bombarding energies and fluxes in thesamples of irradiated stacks. The computer code is under development, for quick andautomatic flux and energy determinations. The first experience shows that in practice only
iterative and interactive approximation can be used to determine the correct flux and energy
values because of the fact that the measured excitation functions are not an exact
mathematical functions, and usually contain different systematical errors.

STAFF and COMPUTERS

Two persons are working on the project in part-time. Hopefully, the man-power will
be increased by an other person by the end of this year.
Computers: Fujitech PC-AT 486 (IBM compatible)
processor 50 Mhz
RAM 4MB
hard disk 210 MB
floppies 3.5" and 5.25"
Exabyte tape unit 5GB
AVR 3000 scanner
Indy Silicon Graphics workstation termial
Graphics Power Challenge trough network.
4 processors
RAM 256MB
hard disk 8GB
DATCD

connected

toaSilicon

REFERENCES FROM 1991
-F. Tarkanyi, F. Szelecse'nyi, P. Kopecky; Excitation functions of proton induced nuclear
reactions on natural nickel for monitoring beam energy and intensity.
Applied Radiation and Isotopes, 42, 513, 1991
-P. Kopecky, F. Szelecsenyi, T. Molnar, P. Mikecz, F. Tarkanyi; Excitation functions ofproton induced nuclear reactions on ""'Ti used for monitoring bombarding beams.
Proceedings of the Sixth Symposium on the Medical Application of Cyclotrons, June 1-4,
1992, Turku, Finland, Ed: L- M. Voipio-Pulkki and U. Wegelius, Turku, 1992.p. A23-P. Kopecky, F. Szelecsenyi, T. Molnar, P. Mikecz, F. Tarkanyi; Excitation functions of(p,xn) reactions on T i ; monitoring of bombarding proton beams. Applied Radiation and
Isotopes 44, 687, 1993.
-F.Tarkanyi ,F. Szelecsenyi, P. Kopecky: Cross section data for proton ,3He- and alpha particle induced reactions on MtNi, ""'Cu and ""'Ti for monitoring beam performance. Nuclear
Data for Science and Technology. Proceedings of International Conference,
Forschungzentrum Jiilich, FRG, 13-17 May ,1991, Ed.: S.M. Qaim, Berlin, SpringerVerlag, 1992, p. 529-F. Tarkanyi, S. Takacs, S.-J. Heselius, O. Solin, J. Bergman;Studies of density reduction in stacked gas targets
Annual Report 1992, Inst. of Nucl. Res. of the Hung. Acad. of Sci.,

Debrecen, Hungary-S. Takacs, L. Vasvary and F. Tarkanyi; Remeasuement and Compilationof Excitation
Function of Proton Induced Reaction on Iron for Activation Techniques, NIM B (acceptedfor publication).
-F. Tarkanyi, S. Qaim, G. Stoklin, M. Sajjad, R.M. Lambrecht, and
H. Schweikert; Excitation function of (p,2n) and (p,n) Reaction and Differential andIntegral Yields of 123I in Proton Induced Nuclear Reactions on Highly Enriched 124Xe. Appl.
Radiat. Isot. 42, 221, 1991.
-Z. Kovacs, F. Tarkanyi, S. Qaim and G. Stoklin; Excitation Function for the Formation ofsome Radioisotopes of Rubidium in Proton Induced Nuclear Reactios on ^Kr, 82Kr and 83Kr
with Special Reference to the Production of 81Rb(81mKr) Generator. Appl. Radiat. Isot. 42,
329, 1991.
-Z. Kovacs, F. Tarkanyi, S. Qaim and G. Stoklin; Production of 6.5h 82mRb via the82
Kr(p,n)-process at a Low-energy Cyclotron-A Potential Substitute for 82Rb. Appl. Radiat.
Isot. 42, 831, 1991.
-F. Tarkanyi, S. Qaim, G. Stoklin, M. Sajjad and R.M. Lambrecht; Nuclear Reaction Cross
Section Relevant to the Production of the 122Xe-122I Generator System using Highly
Enriched 124Xe and a Medium-sized Cyclotron. Appl. Radiat. Isot. 42, 229, 1991.

-F. Tarkanyi, Z. Kovacs and S.M. Qaim; Excitation Function of Proton Induced Nuclear
Reaction on Highly Enriched 78Kr: Relevance to the Production of 75Br and 77Br at a Small
Cyclotron,
Appl. Radiat. Isot. 44, 1105, 1993.
-F. Tarkanyi, Z. Kovacs, S. Qaim and G. Stoklin; Production of 38K via the 38Ar(p,n)Process at a Small Cyclotron.
Appl. Radiat. Isot. 43, 503, 1993.
-F.Tarkanyi ,F. Szelecsenyi, P. Kopecky, T. Molnar, L. Ando, P. Mikecz, Gy. Toth and A.
Rydl; Cross Section of Proton Induced Nuclear Reactions on Enriched l u Cd and I12Cd for
the Production of '"In for Use in Nuclear Medicine. Appl. Radiat. Isot. 45, 239, 1994.
-F. Szelecsenyi, T.E. Boothe, E. Tavano, M.E. Plitnikas and F. Tarkanyi; Compilation of
Cross Section/Thick Target Yields for 66Ga, 67Ga and 68Ga Production Using Zn Targets up
to 30 MeV Proton Energy.
Appl. Radiat. Isot. 45, 473, 1994.
- F. Tarkanyi, F. Szelecsenyi and S. Takacs; Determination of Effective Bombarding
Energies and Fluxes Using Improved Stacked Foil Technique, Acta Radiot. Suppl. 376, 72,
1991.
-F. Tarkanyi, Z. Kovacs, I. Mahunka,O. Solin and J, Bergmann; Excitation Function of theCl(alpha,n)38K reaction Using Gas Targets.
Radiochimica Acta 54, 165, 1991.
35

Appendix 9

Working papers*(see Appendix 5)

*

WP #

Title

1

Conclusions and actions of the 1992 NRDC meeting

2

Pending EXFOR items

3

List of TRANS tapes by 1 April 1994

4

Disturbing mistakes in TRANS tapes

5

Pending EXFOR retransmissions

6

Media for data exchange between centers

7

CINDA manual revision: coding of (2n,f), (n,n'f) and(n,2nf) reactions (memo 4C-3/374 rev.)

8

Documents distribution

9

CPND needs expressed in an IAEA meeting(memo CP-D/246)*

10

Conclusions and actions of the 1991 NRDC meeting

11

Need for a new dictionary transmission format for
EXFOR/CINDA dictionaries*

12

Photonuclear Data (Smolenice meeting 18-21 April 1994)*

13

CPND (Smolenice meeting 18-21 April 1994)

14

Information about Russian evaluated data

15

Memo CP-M/15: Dictionary correction and additions

16

Present status of JENDL project17

Status report of JENDL charged particle data

18

Present status of photonuclear data evaluation at JAERI

19
20

Activities on neutron reaction data at CNDC
Charged-particle and photonuclear data activities
at CNDC
Memo CNDC-25/04/94

*

21
*

22

Memo CP-A/65: Some remarks on old andnot correct data in B-, L-TRANS tapes

23

The current status of CENDL-2

These papers are not reproduced here because they are
distributed either as a CP memo or as part of another report.

-2-

Scientific papers distributed at the meeting *)*)51

Evaluation of (n,2n) reaction cross section on
In-115 and In-113 (V.Manokhin)

52

Systematics of the (n,2n) and (n,3n) reaction excitation
functions (V.Manokhin)

53

Reference input library on nuclear parameters for modelcomputations - Evaluated nuclear parameter library (ENPL)(Su Zongdi et al.)54

The evaluations and calculations of intermediate energy nuclear
data for Fe-56, Cu-63 and Cu-65(p,n) monitor reactions(Zhuang Youxiang)

55

The calculations of photonuclear data (Zhang Jingshang et al.)

These papers are not reproduced in the present report.
Copies may be requested from the Scientific Secretary of the meeting.

Working Paper 2: Pending EXFOR items (dictionary codes, coding
rules)O.Schwerer

1. Proposed codes for dict.36 IND,ZP and CUM5ZP
Memo 4C-4/55 (attached)
Reply: CP-D/245 (attached)
2. Bremsstrahlung cross section in entry 22206 of TRANS 2132 (listing attached)
see Memo 4C-3/368 (attached)(No new codes proposed yet)
3. Conference code 93DUBNSPAs mentioned in memo CP-D/244 of 7 March 1994, entries A0514 and A0515 of
TRANS A029 contain a new conference code, 93DUBNSP, of which the expansion
has not yet been received.
4. General structure of BIB section:
If both coded information and free text are given for a keyword, is it legal
to start with free text and give the code(s) only in one of the following
lines?
There are cases where this could make sense, and it is not explicitly
forbidden in the Exfor Manual. It seems, however, that this was not originallyforeseen and is not accepted by some check programs. Should it be explicitly
forbidden?
There are some (probably not many) cases existing in the master file. The
following is an example where it could make sense:
ERR-ANALYS

GENERAL INFORMATION ON ERROR ANALYSIS(ERR-1 EXPLANATION OF FIRST SYSTEMATIC ERROR(ERR-2)EXPLANATION OF SECOND SYSTEMATIC ERROR

The problem applies in theory to all BIB keywords having coded information.
Real examples may exist for METHOD, DETECTOR and possibly others.

MEMO 4C - 4 / 55
Centr po Jadernym Dannym - CJD
Nuclear Data Centre, Obninsk,
RussiaDATE : February 17,
To:
Distribution
Prom:
S. Mayev
Subject:

Institute of Physics and PowerEngineering
249020 Obninsk, Kaluga region
Russia1994

Modification of nuclide parameters in Diction 27.
New REACTION Quantity codes for Diction 36.

Diction 27:
For nuclide 77-IR-192 we propose introduce code "1" in the field
FLAGS, col. 13, for this nuclide might be used in the REACTION
SF1. This nuclide then would look like
77-IR-192

(13

C

2)

REFERENCE: (J,AE,72,(2),164,9208)
EXFOR ENTRY 41124
For nuclide 23-V-50 we propose introduce code "4" in the field
FLAGS, col. 16, for this nuclide might be used in the REACTION
SF1 when SF2=0. This nuclide then would look like
23-V-50

(1 34

C

)

REFERENCE: (J,YK,,(1),27,92)
EXFOR ENTRY 41118
Diction 36:
For coding and correction EXFOR entries we propose to introduce
new codes for coding fission product yields:
IND,ZP-

most probable value of Fission Fragment charge
for INDEPENDENT fission yield

CUM,ZP-

most probable value of Fission Fragment charge
for CUMULATIVE fission yield

REFERENCE:"RADIOKHIMIYA"(RAK), vol. 4, # 11 page 587, 1962, USSR;"SOV.RADIOCHEM.11 (SRA) ,vol.4, p. 515, 1962.
Exfor ENTRY 41072.
"RADIOKHIMIYA11 (RAK) , vol. 4, # 12 page 711, 1962, USSR;"SOV.RADIOCHEM."(SRA),vol.4, p. 631, 1962.
Exfor ENTRY 41073.

Stanislav A. Mayev
Clearance:

Vassiliy N. Manokhin.

Distribution:
V.McLane
H.Lemmel
J.J.Schmidt

S.Pearlstein
V.Varlamov
F.Chukreev

N.Tubbs
Cai Dunjiu

Memo CP-D/245
April 12, 1994
To:

Distribution

From:

O. Schwerer + M. Lammer 'Subject:

1. Dictionary update
2. Proposed codes IND,ZP and CUM,ZP

1. We are sending out the dictionary transmission tape 9067 containing thechanges/additions requested in memos 4C-4/54, 55, CP-C/206, 207 and others.
In addition, the following new codes are introduced:
Diet. 3 (Institutes)
3MAKMAK
3SNSN

Macedonia
SenegalDiet. 5 (Journals)
AJSE
BJE
JAE
RJP

Arab.J.Sci.Eng.
Bezp.Jad.Energ.
Jadernaja Energetika
Romanian J. Phys.

Diet. 6 (Reports)
CNEA-CAB-IT-

Bariloche Internal R<

A complete list of the update is attached.

Distribution:
M.R. Bhat, NNDC
N. Tubbs, NEA-DB
V.N. Manokhin, CJD
F.E. Chukreev, CAJaD
T. Tendow, RIKEN
V. Varlamov, CDFE
M. Chiba, JCPRG
Zhang Jingshang, IAE-CP
V. McLane, NNDC

NDS: R. Arcilla
S. Ganesan
M. Lammer
H.D. Lemmel
P. Oblozinsky
A. Pashchenko
O. Schwerer
H. Wienke
3 spare copies

.2.
2.

RE: Memo 4C-4/55: proposed codes IND,ZP

andCUMrZP

The proposal should be rejected. Reason:
ZP is a parameter of the charge distribution for a given fragment mass,
for which independent and cumulative yields are defined. In practice,
independent and/or cumulative yields are measured, and ZP is derived.
However, the charge distribution for a given mass is the same forindependent and cumulative yields, and hence the parameter _ZP_ is also
the same (i.e. independent of the type of yield measured). Therefore"IND" and/or "CUM" are superfluous. See LEXFOR, Fission Yields, page 3.

Background:1) a) IND and CUM (SF5) stand for measured independent and cumulative yields.
b) ZP is a derived quantity, i.e. a parameter of an empirically assumed
and fitted distribution.
c) "fractional", as in LEXFOR, stands for a normalized distribution(integral = 1)
2) It is a semi-empirical assumption that independent yields of fragmentswith different charge and the same mass have a Gaussian distribution (apartfrom "odd-even effects"). The parameters of that (normalised) distibution
are the most probable charge ZP (location of maximum) and the width.
When several inedependent yields of a given mass are measured, a Gaussian
can be fitted to them, and ZP can be derived.
The cumulative yield of a fragment, Yc(Z,A), is defined as the sum of
it's own independent yield Yi(Z,A) and those of it's (beta-decaying)precursors Yi(Z-x,A), x=l,2,(apart from delayed neutron emission):Yc(Z,A) = Yi(Z,A) + Yi(Z-l,A) + Yi(Z-2,A) +Hence the cumulative yields are assumed to be distributed as the integralof the Gaussian distribution for the independent yields. Measured cumulative
yields can therefore be fitted to that integral Gaussian, and ZP can bederived. But the Gaussian and therefore ZP are identical for independentand cumulative yields. There is no independent or cumulative ZP!
3) Coding in EXFOR:ZP is a deduced quantity, obtained from measured independent or
cumulative yields. Therfore:a) The measured independent or cumulative yields should be given inanother subentry.
b) ZP should be coded without any code in SF5. The STATUS code shouldbe "dependent" with the SE number given where the measured yields
are coded in the data table.

ALTER
1CANQU
1CANUWO
3MAKMAK3SN SN
4RUSEPA
4RUSTPCAJSE

MEMO 4C-4/54,55,CP-C/206,207 ET AL.
(QUEEN'S UNIV., KINGSTON, ONTARIO)
30000003000201(UNIV.OF WESTERN ONTARIO, LONDON, ONTARIO)
30000003000251(MACEDONIA)
30000003009191(SENEGAL)
30000003010151(EXPERIMENTAL PHYSICS INST., ARZAMAS)
30000003011751(TECHNICAL PHYSICS INST., CHELYABINSK)
30000003012281(ARAB.J.SCI.ENG.)
3SAR3000000500064I
ARABIAN JOURNAL FOR SCIENCE AND ENGINEERING
30000005
2
BJE(BEZP.JAD.ENERG.) BEZPECNOST JADERNE ENERGIE3CZR30000005001471(SAFETY OF NUCLEAR ENERGY). CONTINUATION OF JE
30000005
2
JOINT CZECH-SLOVAK J., PRINTED IN PRAGUE, STARTED 1993 30000005
3
JAE(JADERNAJA ENERGETIKA)
4RUS30000005003391
JE(JAD.ENERG. (PRAGUE)) JADERNA ENERGIE3CSR3000000500346X==CONTINUED FROM 1993 AS BJE
30000005003461===NOTE: THE CINDA CODE IS JPAL
30000005003911===NOTE: THE CINDA CODE IS JPGL
30000005004021===NOTE: THE CINDA CODE IS JPRA
30000005004141===NOTE: THE CINDA CODE IS JPRC
30000005004171===NOTE: THE CINDA CODE IS JPRL
30000005004211===NOTE: THE CINDA CODE IS JPRS
30000005004251
RJP(ROMANIAN J.PHYS.) ROMANIAN JOURNAL OF PHYSICS
3RUM3000000500711I
CONTINUATION OF RRP, STARTING WITH VOL.37(7) , 1992
30000005
2
RRP(REV.ROUM.PHYS.)
3RUM3000000500724X===CONTINUED AS ROMANIAN J.OF PHYSICS (RJP)
30000005007271
FROM VOL. 37 (7), 1992
30000005
2
EVALUATED NUCLEAR DATA FILE (ENDF) REPORTS
1USAUSA3000000600223I
ENDF3ARGCNE3000000600442I
CNEA-CAB- ITCENTRO ATOMICO BARILOCHE, INTERNAL REPORTS
CINDA INDEX AND LIST OF PARTIC.PUBL.IN NEANDC-312
30000007013411
SELECTED PAPERS PUBL. IN IZV 56 (11), 57 (1)3000000701349C(INT.SYMP.ON NUCL.DATA EVAL.METHODOLOGY, BNL, OCT.1992)30000007013521
92BNL(INT.SYMP.ON NUCL.DATA EVALUATION METHODOLOGY,
30000007
2
BROOKHAVEN NATIONAL LABORATORY, USA, 12-16 OCT.1992)
30000007
3
PROCEEDINGS PUBL.BY WORLD SCIENTIFIC, SINGAPORE
30000007
4
(1 34
CS )
23-V-50
3000002700209C(13
Cl)
56-BA-133
3000002700942C(3
C)
66-DY-159
3000002701140C
C 2)
77-IR-192 (133000002701366C
ENDALTER

Memo 4C-3/368
18 May 1993
To:

Distribution

From:

H. Wienke and O. Schwerer

Subject:

1. Bremsstrahlung cross section in entry 22206
2. Comments on TRANS 2132

1. Bremsstrahlung cross section in entry 22206
In entry 22206 of TRANS 2132 Bremsstrahlung cross sections for the n-p reaction arecompiled, using REACTION codes 1-H-1(N,G+N), 1-H-1(N,G+P), 1-H-1(N,INL), which
do not conform to present compilation rules for light particle reactions.
We believe that this is a new data type, and - if such data are to be compiled in
Exfor - a new way of coding should be proposed.

Distribution:
C.L. Dunford, NNDC
N. Tubbs, NEA-DB
V.N. Manokhin, CJD
V. McLane, NNDC

NDS: R. Arcilla
S. Ganesan
M. Lammer
H.D. Lemmel
A. Pashchenko;'. O. Schwerer
H. Wienke
3 spare copies

TRANSENTRY
SUBENTBIB
REFERENCETITLE
AUTHOR

3000
9404120000000000000
93032922206
2220600000001
93032922206001
2220600100001
49
162220600100002(J,NP/A,481,424,88)2220600100003-THE HARD NEUTRON-PROTON BREMSSTRAHLUNG AT 76 MEV.
2220600100004(C.DUPONT,C.DEOM,P.LELEUX,P.LIPNIK,P.MACQ,A.NINANE,
2220600100005
J.PESTIEAU,S.P.KITWANGA,P.WAUTERS)
2220600100006
INSTITUTE (2BLGLVN)
2220600100007(CYCLO)
2220600100008
FACILITY
.AN
80
MEV
10
MICROAMP
PROTONBEAM
BOMBARDEDA
2220600100009
INC-SOURCE
1 CM THICK NATURAL LITHIUM TARGET. NEUTRONS PRODUCED 2220600100010
AT 0 DEGREES WERE SELECTED BY A 1.6 M LONG CONICAL
2220600100011
IRON COLLIMATOR OF 11 - 20 MM ENTRANCE - EXIT DIAME- 2220600100012
TER. IN ADDITION, THERE WERE TWO HALO COLLIMATORS, 20 2220600100013
CM LONG AND 25 AND 28 MM IN DIAMETER. THE NEUTRON IN- 2220600100014
TENSITY AT 2.6 M FROM TARGET WAS ABOUT 6E+6 PER SEC. 2220600100015
2220600100016(TOF ) THE ENERGIES OF THE NEUTRONS WERE DETERMINEDMETHOD
2220600100017
WITH TIME-OF-FLIGHT.
2220600100018(COINC) A SCINTILLATOR TELESCOPE WAS USED TO DETECT
2220600100019
THE PROTONS.
(SCIN ) A THIN 0.1 MM SCINTILLATOR OF 3 CM DIAMETER UP- •2220600100020
DETECTOR
2220600100021
STREAM TO THE SAMPLE VETOED ON CHARGED PARTICLES IN
THE NEUTRON BEAM. 27 CM BEYOND THE TARGET A 12 CM DIA- •2220600100022
METER BY 0.2 MM THICK SCINTILLATOR, WITH A 34 MM DIA- 2220600100023
METER HOLE TO PROVIDE PASSAGE FOR THE NEUTRON BEAM,
2220600100024
FIRED ON CHARGED PARTICLES. 1.25 M FROM THE HYDROGEN 2220600100025
TARGET A 40 X 40 CM2 SCINTILLATOR OF 1 CM THICKNESS
2220600100026
ACTED AS A PROTON ENERGY DETECTOR. PROTONS OF ENERGY 2220600100027
LARGER THAN 33 MEV WERE VETOED BY ANOTHER 40 X 40 CM2 2220600100028
SCINTILLATOR OF 0.5 CM THICKNESS, PLACED IMMEDIATELY 2220600100029
AFTER THE E DETECTOR. THE NEUTRON DETECTOR WAS A
2220600100030
40 X 40 CM2 PIECE OF SCINTILLATOR OF 5 CM THICKNESS. 2220600100031
A 56 MM HOLE WAS CUT IN EACH DETECTOR FOR THE PASSAGE 2220600100032
OF THE NEUTRON BEAM.
2220600100033
2220600100034(1-H-1(N,G)l-H-2,,SIG)
MONITOR
2220600100035.A LIQUID HYDROGEN TARGET WITH A VOLUME OF 35 MM DIASAMPLE
2220600100036
METER AND 5 MM THICKNESS WAS PLACED 2.6 M FROM THE
2220600100037
NEUTRON SOURCE. THE TARGET VOLUME WAS LIMITED BY 62220600100038
MICROMETER THICK ALUMINIZED MYLAR WINDOWS.
CORRECTION .CORRECTIONS WERE APPLIED FOR NEUTRON REACTIONS IN THE 2220600100039
PROTON DETECTORS AND FOR THE FINITE EFFICIENCY OF THE 2220600100040
2220600100041
NEUTRON DETECTOR.
2220600100042
ERR-ANALYS (DATA-ERR).THE ACCEPTANCE OF THE DETECTOR SYSTEM AND THE EFFICI- 2220600100043
ANALYSIS
ENCY OF THE NEUTRON DETECTOR WERE CALCULATED WITH MON -2220600100044
2220600100045
TE CARLO CODES.
.ALSO DIFFERENTIAL DATA, WITH RESPECT TO THE AZIMUTHAL 2220600100046
COMMENTANGLE BETWEEN THE NEUTRON AND THE PROTON WERE TAKEN, 2220600100047
2220600100048
AND IS PRESENTED IN A FIGURE.
2220600100049.DATA TAKEN FROM MAIN REF.
STATUS
2220600100050
HISTORY(921213C) N.O.
2220600100051(930329E)
2220600100052
ENDBIB0492220600100053
COMMON3
22220600100054
MONIT
MONIT-ERR
2220600100055
MICRO-B
MICRO-B
2220600100056
1.4200E+01 2.0000E-01
2220600100057
ENDCOMMON
302220600199999
ENDSUBENT
56
02220600200001
SUBENT
22206002
9303292220600200002
BIB
3
42220600200003
REACTION(1-H-1(N,G+N)1-H-1, ,DE,N)STATUSHISTORY.DATA TAKEN FROM MAIN REF.
(921213C) N.O.
(930329E)
ENDBIB
40
NOCOMMON
0
0
DATA
4
12
EN
E
DATA
DATA-ERR
MEV
MU-B/MEVMEV
MU-B/MEV
7.6500E+01 1.1000E+01 3.0400E-02 6.0000E-03
7.6500E+01 1.3000E+01 2.7100E-02 6.0000E-03
7.6500E+01 1.5000E+01 4.8900E-02 6.4000E-03
7.6500E+01 1.7000E+01 4.5100E-02 5.8000E-03
7.6500E+01 1.9000E+01 5.0200E-02 6.0000E-03
7.6500E+01 2.1000E+01 3.2800E-02 4.9000E-03
7.6500E+01 2.3000E+01 1.9800E-02 3.8000E-03
7.6500E+01 2.5000E+01 1.6100E-02 3.3000E-03
7.6500E+01 2.7000E+01 1.3900E-02 3.1000E-03
7.6500E+01 2.9000E+01 6.2000E-03 2.0000E-03
7.6500E+01 3.1000E+01 6.2000E-03 2.2000E-03
7.6500E+01 3.3000E+01 4.6000E-03 2.0000E-03
ENDDATA
14
0
ENDSUBENT
023
SUBENT
93032922206003
BIB
4
3(1-H-1(N/G+P)O-NN-1,,DE,P)
REACTIONSTATUS.DATA TAKEN FROM MAIN REF.
HISTORY(921213C) N.O.
(930329E)
ENDBIB
40
NOCOMMON
0
0
DATA
4
9
EN
E
DATA
DATA-ERR
MEV
MEV
MU-B/MEVMU-B/MEV
7.6500E+01 1.5000E+01 3.4300E-02 5.1000E-03
7.6500E+01 1.7000E+01 5.5900E-02 6.2000E-03
7.6500E+01 1.9000E+01 6.2100E-02 6.0000E-03
7.6500E+01 2.1000E+01 6.0100E-02 6.9000E-03
7.6500E+01 2.3000E+01 3.5400E-02 6.0000E-03
7.6500E+01 2.5000E+01 1.5600E-02 5.1000E-03
7.6500E+01 2.7000E+01 2.4900E-02 4.6000E-03
7.6500E+01 2.9000E+01 1.0300E-02 3.3000E-03
7.6500E+01 3.1000E+01 2.2000E-03 2.9000E-03
11
0
ENDDATAENDSUBENT
20
0
SUBENT
22206004
930329BIB
34REACTION(1-H-1(N,IN!•) , ,SIG)
STATUS.DATA TAKEN' FROM MAIN REF.
HISTORY(921213C) N .0.
(930329E)
ENDBIB
40
NOCOMMON
0
0
DATA
3
1
EN
DATA
DATA-ERR
MEV
NB
NB
7.6500E+01 6.0210E+02 3.2800E+01
ENDDATA
3
0
ENDSUBENT
120
ENDENTRY
4ENDTRANS
1

2220600200004
2220600200005
2220600200006
2220600200007
2220600200008
2220600200009
2220600200010
2220600200011
2220600200012
2220600200013
2220600200014
2220600200015
2220600200016
2220600200017
2220600200018
2220600200019
2220600200020
2220600200021
2220600200022
2220600200023
2220600200024
2220600299999
2220600300001
2220600300002
2220600300003
2220600300004
2220600300005
2220600300006
2220600300007
2220600300008
2220600300009
2220600300010
2220600300011
2220600300012
2220600300013
2220600300014
2220600300015
2220600300016
2220600300017
2220600300018
2220600300019
2220600300020
2220600300021
2220600399999
2220600400001
2220600400002
2220600400003
2220600400004
2220600400005
2220600400006
2220600400007
2220600400008
2220600400009
2220600400010
2220600400011
2220600400012
2220600400013
2220600499999
2220699999999
9999999999999

Working Paper 3:

List of last TRANS tapes by 1 April 1994
(update of memo CP-D/243 of 17 December 1993)

last tapeseriescoming fromnumber

dated

1
2

NNDC
NEA-DB
NDS

94-02-16
94-03-07
94-03-01
93-11-03
92-07-29

4
V

NDS

1256
2133
3091
4094
V025

A
C
D
E
R
S

CAJaD
NNDC
NDS
Sapporo
RIKEN
IAE-CP

A029
C012
D018
EOll *)
R008
S007

93-12-10
88-12-27
93-09-30
94-03-11
93-07-23
93-09-30

G
L
M

NDS
NNDC
CDFE

G007
L004
M017

92-02-14
91-06-13
93-03-25

3

*)

CJD

TRANS E010 and EOll were not yet added to the NDS master file because ofpending corrections. The last processed TRANS tape from Sapporo was E009 dated
91-09-11.

Working Paper 4: Disturbing mistakes in TRANS tapes
O.Schwerer

The following is a selection of some typical mistakes. Many others are mentioned in memos
4C-1/215-219, 4C-3/366,368,369,372, and CP-D/233,234,236,241,244.

- Missing incident particle energy- Redundant incident particle energy (e.g. EN-MIN, EN-MAX in COMMON section
and EN in DATA section)- Secondary energy given only in free text (in particular for ground state)- PAR given in REACTION SF5 when integral cross section was measured- Inconsistency between the information given (or missing) underthe BIB keyword INC-SPECT, the data headings (EN vs. EN-MEAN etc.),
and modifiers in REACTION SF8 (MXW, SPA, AV and others)- a number of special problems with fission-product yield measurements wasoutlined by M.Lammer in memo 4C-3/369- For E-format data, the experiments must be rigt-adjusted within the data field

Working Paper 5: Pending EXFOR retransmissions
O.Schwerer, 8 April 1994

Please find attached a reminder as for which EXFOR entries are still pending forretransmission as requested by NNDC and NDS from NNDC, NEA-DB, NDS, CJD, CAJaD,
CDFE and RIKEN.
When mistakes are found in TRANS tapes, retransmission is requested for those cases
where the correction to be done is not obvious. It is appreciated that many requested
corrections were retransmitted since the last meeting. However, a number of requests forretransmission remained without response (sometimes for several years) for the EXFOR
entries listed. May we ask each center to review this list, update the listed entries andretransmit them.
In fulfillment of Action 37 of the 1992 NRDC meeting, the reason for the oldest
pending requests for retransmission was reviewed for Areas 1, 2 and 4. The entries concerned
were checked and as a consequence, some of the requests were deleted because either the
subentry had been deleted meanwhile, or because no obvious error could be located. In theremaining cases, the mistakes still in the file are briefly summarized in the list given below(only for those very old entries; details on the more recent ones can be found in therespective 4C- or CP-memos).

LIST OF PENDING RETRANSMISSIONS
I. Some very old entries which were checked once moreTRANS

ACCESSION #Comments

1101
1119
1136
1136
1136

12627002
11281010
12355002
12355006
12355007DATA section mixed up from line 69
EN values (exponent?) wrong from line 21
wrong REF code CRR-. Probably CRP- or CRRP-

2081
2089
2100
2100
2100
2100
2100
2102
2110
2110
2110
2110

20775003
20742005
21904002
21904003
21904004
21904005
21914003
21944002
21993002
22000all
22001021
22001022

multiple monitor, repeat REACTION
ASSUM3: empty data column
secondary energy missing

4043
4053
4055
4055
4056
4060
4060
4060
4060
4060

40580002
40577001
40792001
40793001
40576003
40528009
40611003
40611004
40611005
40611006

ii

PAR in SF5 and secondary energy missingII

numbers in DATA section mixed up
DA in SF6 probably wrong
wrong units and indep. variable not monotonic
KT (replacing EN) must not be given in DEG-K
EN-MEAN requires modifier in SF8 and BIB def.
several wrong REACTION codes
INSTITUTE code

DECAY-DATA inappropriate
REACTION wrong, Common section wrong
EN given twice

II. More recent cases (see respective memos for requested corrections)TRANS

ACCESSION #TRANS

ACCESSION #

1217
1229
1230
1230
1232
1232
1232
1233
1233
1233
1233
1233
1242
1242

10142002
13119002
12991002
12991003
11010001
13132001
13156001
13066003
13066004
13073002
13092002
13092003
13195002
13195003

2117
2117
2117
2117
2117
2117
2117
2117
2117
2117
2118
2118
2122
2122

22027005
22031151
22031152
22031153
22031154
22031155
22031156
22031157
22031158
22031159
22050001
22039002
22032002
22032003

TRANSACCESSION #TRANS

ACCESSION #

2122
2122
2128
2128
2128
2128
2128
2129
2129
2129
2129
2129
2129
2129
2129
2129
2132
2132
2132
2132
2132
2132
2132
2132
2132
2132
2132
2132
2132
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133

22052004
22057003
22156015
22157055
22157057
22157073
22157087
21928001
22116002
22116003
22116004
22129001
22130001
22143002
22143003
22161002
22200003
22205002
22205003
22205004
22218002
22218003
22218004
22218005
22223002
22225002
22225003
22225004
22228002
22228002
22228003
22228004
22228005
22228006
22228007
22228008
22232002
22233002
22234001
22234002
22234003
22234004
22234005
22234006
22234007
22238001
22238002
22238003
22238004
22238005
22238006
22238007
22238002
22239002
22239003
22241002
22241003
22241004
22241005
22241006
22241007

2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133
2133

22241008
22241009
22245002
22245003
22245004
22245005
22245006
22245007
22245008
22246002
22246003
22246004
22246005
22246006
22247002
22247003
22249002
22250002
22250003
22250004
22250005
22250006
22250007
22251002
22251003
22251004
22251005
22251006
22251007
22251008
22251009
22251010
22252002
22252003

3061
3071
3078
3078
3084
3084
3084
3084
3084
3084
3087
3087
3087
3087
3088
3088
3088
3088
3088
3088
3088
3088
3089
3089
3089

30755010
30932003
30016002
30218002
30610001
30711003
30986005
30991002
30991003
30991004
30739004
30739005
30739006
30808003
30904004
30939012
32591001
32591002
32591003
32591004
32592001
32593001
30735006
30735007
30974002

TRANSACCESSION #TRANS

ACCESSION #

4066
4069
4075
4075
4082
4084
4084
4084
4084
4084
4084
4084
4084
4084
4085
4085
4085
4085
4085
4085
4085
4085
4085
4085
4085
4085
4085
4085
4085
4085
4086
4086
4086
4087
4087
4087
4087
4087
4087
4087
4087
4087
4087
4087
4087
4088
4088
4088
4088
4088
4088
4088
4088
4088
4088
4088
4088
4088
4088
4088
4088

40915003
40930001
40965001
40974003
40541001
40776002
40877002
40877003
40877004
40877005
40877006
40894002
40894003
40894005
40083002
40083003
40083006
40083007
40083009
40145003
40173008
40173014
41055002
41055003
41055004
41055005
41055006
41055007
41056003
41059003
41072002
41073002
41073003
41086002
41086003
41086004
41086005
41086006
41086007
41086008
41086009
41086010
41086011
41086012
41086013
40245007
40346013
40346014
40346018
40449002
40539001
40936001
41063002
41065003
41067002
41067003
41067004
41074002
41077002
41088009
41088011

4088
4088
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4089
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4090
4091
4091
4091
4091
4091
4091
4091
4091
4091
4091
4091
4091
4091
4091
4092
4092
4092
4092
4092
4092

41088014
41089002
40551001
40551002
40551004
40551006
40602002
40655002
40655003
4066700740667008
40667009
40728005
40728006
40728007
40728008
40728009
40728010
40728014
40891002
41095002
40329003
40329004
40420003
40420004
40420008
40420009
40420047
40489003
40489004
40916002
41047001
41085002
41085003
41087002
41087003
41087004
41100004
41100005
41100006
41100007
40938001
40944001
40956007
41084001
41084002
41084003
41084004
41084005
41084006
41084007
41101002
41104002
41104003
41104004
40199002
40199005
40389003
40389004
40389007
40389009

TRANSACCESSION #TRANS

ACCESSION #

4092
4092
4092
4092
4092
4092
4092
4092
4092
4092
4092
4092
4092
4092
4092
4094
4094
4094
4094
4094
4094
4094
4094
4094
4094
4094
4094
4094

40389010
40389013
40389016
40389017
40389018
40389019
40420001
40963002
40972002
41042002
41042004
41042006
41042007
41042008
41110001
41103001
41103007
41109002
41109003
41109004
41109005
41109006
41109008
41109009
41109010
41120002
41120003
41120004

C007
C010
C011

C013
C013

C0295001
C0328007
C0306004
C0316002
C0333002
C0345001
C0412012
C0373001
C0399001

L003
L003
L004
L004

L0006010
L0011002
L0052005
L0052006

A017
A017
A017
A018
A019
A019
A019
A019
A019
A019
A019
A020
A020
A020
A020
A020
A020
A020
A020
A021
A021
A021
A021
A022
A027
A027
A029

A0229004
A0317004
A0329002
A0320002
A0178001
A0198001
A0202002
A0202003
A0202004
A0345003
A0345010
A0319023
A0319030
A0322005
A0347004
A0352004
A0363001
A0364001
A0365001
A0387007
A0388001
A0393002
A0393004
A0399001
A0366001
A0497008
A0340006

M011
M011
M011
M011
M011
M012
M012
M012
M012
M013
M013
M013
M013
M013
M013
M014
M014
MO 14

M0028006
M0028007
M0035020
M0046002
M0046003
M0080001
M0098002
M0140011
M0140012
M0152006
M0244002
M0291002
M0291003
M0293002
M0293003
M0327016
M0333001
M0340001

R008
R008
R008

R0049002
R0049003
R0049004

con
con
C011

con

Working Paper 7:
Memo 4C-3/374 (Rev. 2)
21 April 1994
To:

Distribution

IIFrom:M. Lammer

Subject:

CINDA manual revision: coding of (2n,f), (n,n'f) and (n,2nf) reactions

CINDA Action No. 59 from 1992 NRDC meeting: Coding hints for reactions (2n,f)and (n,n'f): Proposed manual revision for pages II.2.8 (hints for coding such cases) andII.2.17 (note under the heading "fission quantities").
Page n . 2 . 8 :(2n.f) reaction
In this process, 2 neutrons are captured almost simultaneously before the compound nucleus
undergoes fission. Cross sections for this process are entered under the target nucleus with
an appropriate comment, e.g.: "(2N,F)" or "(2N,F) REAC".
For other fission quantities like NU, SFN, NFY, FRS, etc., the compound nucleus after
capture of 2 neutrons (Z,A+2) is essential. This is the same as after (n,f) reaction for thetarget nucleus (Z,A+1). Therefore, CINDA entries should be made for a "target nucleus"(Z,A+1) with the corresponding quantity (NU, NFY, etc.). The comment should containthe real target nucleus and "(2N,F)" or "(2N,F) REAC" or "YLD FROM U235 (2N,F)" etc.
(n.n'f) reaction
The (n,n'f) reaction consists actually of 2 consecutive processes: inelastic scattering to an
excited level of the residual ( = target) nucleus followed by fission from that excited level.
2 cases have to be distinguished:
In the case of instant fission from a level with negligible lifetime (second chance fission), allquantities should be entered for the target nucleus as for (n,f) reactions.
If the (n,n') reaction leads to the formation of a spontaneously fissioning (shape) isomer, thatisomer has to be considered separately, and the coding depends on the quantities measured:
Distribution:
M.R. Bhat, NNDC
N. Tubbs, NEA-DB
V.N. Manokhin, CJD
V. McLane, NNDC

NDS: R. Arcilla
S. Ganesan
M. Lammer
H.D. Lemmel
P. Oblozinsky
A. Pashchenko
O. Schwerer
H. Wienke
3 spare copies

Memo 4C-3/374 (Rev.)
1994-04-21
Page 2
Cross sections for the whole process: entries should be made for the target nucleus andquantities NF or RIF and DIN (since it is a partial inelastic scattering cross section) with theincident neutron energy and appropriate comments, e.g.: "(N,N'F)" or "(N,N'F) REAC" or"SIG FOR (N,N'F)".
Other fission quantities concern only the spontaneously fissioning isomer. Entries should bemade for that isomer (in CINDA the same as the target nucleus), the quantity measured and"SPON" for the energy. An appropriate comment is required, e.g.: "SPONT FISSISOMER" or "FROM ISOMER AFTER (N,N')tt or "FROM U235(N,N')U235M(SF)" or"FROM (N,N'F)". If no information on the (n,n') reaction is given, no corresponding entry
for DIN should be made.
If the inelastic scattering cross section for the formation of the spontaneously fissioning
isomer is given together with other fission quantities, entries should be made for the target
nucleus and the (n,n') reaction as well as for the reported quantities for the spontaneously
fissioning isomer as above, with appropriate comments.
(n.2nf) reaction
In the (n,2nf) reaction, 2 neutrons are emitted before fission occurs (third chance fission).
The considerations of the processes and coding rules for CINDA follow those of the (n,n'f)reaction.
Page BL.2.17 (at top of page before NF):
Fission quantities(2n,f) reaction: cross sections are entered for the target nucleus with appropriate comments.
Other quantities like NU, SFN, NFY etc. are entered for a "target nucleus" (Z,A+1) withappropriate comments containing the real target nucleus (Z,A). See page n.2.8 for details.
(n,n'f) reactions with formation of a spontaneously fissioning isomer: cross sections areentered with NF or RIF and DIN for the target nucleus. All other quantities are entered forthe spontaneously fissioning isomer. If a spontaneously fissioning isomer is not formed, allquantities are entered for the target nucleus as for (n,f) reactions. Information on thereaction has to be given in the comments. See page II.2.8 for details and coding hints.
The coding of (n,2nf) reactions corresponds to that of (n,n'f).
Additional revision of Page n.2.11:
under DIN Diff Inelast:

Definition: Angular distributions or energy spectra of
inelastically scattered neutrons, or partial cross-sections.
Examples of use:
4) cross-section for (n,n'f) reaction(see also pages n.2.8 and n.2.17)

Working Paper 8:

Documents Distribution
The topic of distribution of nuclear data related documents had been a matter of
INDC/NEANDC. Since NEANDC was discontinued, INDC referred the topic to be
discussed between NDS and NEA/DB, but it also concerns some more of the centers present
at the NRDC Meeting.
Recently, the most active contributors of documents for distribution as INDC reports
were Japan, China and Russia. We wish to appreciate this. For further documents kindly
note the number of copies required for the different distribution schemes, as given in theattached table.
The number of reports received from US/Canada or from Europe/area 2 hasdecreased significantly.
Within the community of nuclear reaction data scientists, the free distribution ofcertain report literature had been an essential part of scientific communication. It should be
reviewed whether and how this should be continued.
Topics of such reports were--annual progress reports (as submitted to DOE, to NEANDC/INDC, etc);
lab reports on certain experimental or data evaluation activities;
reports describing contents and/or format of a nuclear data library;
meeting proceedings;
certain newsletters;
and others.

Traditionally, such reports received a code such as INDC(USA)-123 with a
distribution code character behind. While it is useful to recognize, by this report code, what
distribution is received, it is also possible to distribute reports without an INDC code printed
on the cover, in order to avoid that a document carries too many different report codes.
We have a "G" distribution which goes essentially to INDC members and data center
heads; and an "L" distribution which goes to selected scientists in the major countries. We
can also establish special distributions such as "scientists interested in fission-products".
When submitting reports to NDS for distribution, kindly give clear indication what
distribution is wanted, in order to avoid duplicate distribution.
Example:In the case of a US report: L distribution to all countries except USA;or L distribution to areas 3 and 4 only (assuming that area 2
distribution is done by NEA).
In the case of a Chinese report: L distribution except China.
Etc.

See the attached list, how many copies are required for which distribution.

Working Paper 11:

Need for a new transmission format for EXFOR/CINDA dictionaries
O.Schwerer
I. BackgroundSome years ago, NNDC developed an internal dictionary system ('DANIEL')
specifically taylored to the NNDC EXFOR/CSISRS system as implemented in the VAX/VMS
environment. (Since this was an internal system not affecting the other centres, no agreement
was required.)For updating the DANIEL database, the dictionary transmission tapes distributed by
NDS are used. However, since DANIEL is only partly compatible with the originally agreed
dictionary formats, the updating can at present only partly be done by a computer program.
The person in charge has to do some non-trivial manual editing every time the database is
updated; this concerns not only the modifications of the current update, but to a large extent
some unchanged parts of the dictionaries which are treated differently in the 2 systems.
After NDS has taken over the NNDC EXFOR system in 1992, NDS is faced with thesame problem. At the 1992 NRDC meeting, NDS volunteered to design a new dictionarytransmission format fulfilling the needs of both the agreed IBM system and DANIEL. It
turned out, however, that it is not sufficient to design a new transmission format, because
neither of the 2 dictionary systems contains the complete information needed: the IBM
dictionaries don't contain e.g. the numerical quantity equivalents introduced in DANIEL,
whereas DANIEL is lacking all the free text information given in the IBM dictionaries.
Therefore it will probably be necessary to design a new "super-dictionary" system
containing all the information required, from which the dictionary files for both systems canbe extracted. This, a rather different task from the one originally anticipated, is not yet done
because we underestimated both the complexity of the problem and the time it would take
NDS to become fluent in all its VAX operations.
II. What is needed?
- Who needs the dictionary TRANSmission tapes in the traditional (IBM) format?
- How is the update done at NEA-DB?
- How are the CPND and Photonuclear centres dealing with dictionary updates?
- Can we simplify the update procedure for those (2?) centres using DANIEL, to minimize
any duplication of efforts?
- One of the most important technical questions: The free text information contained in many
dictionaries in the IBM version is very important information for the Exfor compilers andmust be kept in some way. Other cases where the IBM dictionaries contain more information
than DANIEL are dictionaries 7 and 36, where in the IBM dictionaries expansions longer
than 1 line exist.

Comparison of the VAX dictionary database (DANIEL) with the original IBM dictionary format

Notes:- All DANIEL dictionaries contain 2 additional internal codes:- STATUS (one of the following: CIN, EXT, INT, OBS, PRE, PRO, TRA)
- date of entry or last update- Most IBM dictionaries contain some free text explanations (important information for the EXFOR/CINDA compilers)
which is missing in DANIEL.
- Sorting within dictionaries: in DANIEL codes are always sorted alphabetically. In the IBM system, codes are
sorted by various criteria depending on the contents of the particular dictionaries, and group headings
in free text may be given.

Diet.#

VAX

IBM

1

SYSTEM IDENTIFIERS
Additional keywords
Missing: essential free text
(definition of N1,N2,..)SYSTEM-IDENTIFIERS

2

INFORMATION IDENTIFIERS
INFORMATION IDENTIFIER KEYWORDS
Additional: internal num.equivalentMissing: elaborate free text explanations

3

INSTITUTE CODESINSTITUTES (SORTED BY CODE)

Lower case expansions (Area 1 only)
4

REFERENCE TYPE

TYPE OF REFERENCE

5

JOURNAL CODES
Missing: important free text
REPORT CODES
Missing: important free text

JOURNALS (SORTED BY CODE)

BOOK AND CONFERENCE CODES
Missing: long expansions
Missing: important free text

BOOKS AND CONFERENCES

67REPORTS (SORTED BY INSTITUTE)ELEMENTS

ELEMENTSCOMPOUNDS

This dictionary does not exist in
DANIEL. Compounds are included indiet.27 (Nuclides AND COMPOUNDS)

10STANDARD REACTIONS (CSISRS)
There is no comparable dictionary
in the IBM system.

(old diet.10 deleted)

11

FORBIDDEN REACTIONS (CINDA)
There is no comparable dictionary
in the IBM system.

(old diet.11 deleted)

12

CINDA QUANTITIESThis is diet.42 in the IBM system.
Missing: free text explanations(old diet.12 deleted)

13

REACTION TYPE (for Dictionary 36)
Same dictionary number used for
different type of information.
There is no comparable dictionary
in the IBM system.

PARTICLES

14

REACTION DIMENSIONS (for Dictionary 36)
There is no comparable dictionary
in the IBM system.

(old diet.14 deleted)

15

HISTORY CODESHISTORY16

STATUS CODES
Additional: internal num.equivalentMissing: elaborate free text explan.

STATUS

17

RELATED REFERENCE CODES
Missing: free text explanation

REL-REF SUBFIELD 1

18

FACILITY

FACILITY
The structuring of information in thisand some of the following dictionaries

was transmitted as approved at the 1992
NRDC meeting, but is not preservedin DANIEL.
19INCIDENT SOURCESOURCE OF INCIDENT PARTICLES20ADDITIONAL INFORMATION
Missing: free text explanation

ADDITIONAL RESULTS

21

METHODMETHOD
Missing: free text explanations

22

DETECTORSDETECTOR
Missing: free text explanations

23

ANALYSISANALYSIS

24

DATA HEADINGS
Additional: 3 internal flags
Missing: free text explanations

DATA-HEADING KEYWORDS

25

DATA UNITSDATA-UNIT KEYWORDS27

NUCLIDES AND COMPOUNDS
Additional:
CINDA code; internal num.equivalent;
spin; abundance/atomic weight;
includes compounds (diet.9 in IBM
system)NUCLIDES

INCIDENT PARTICLES (REACTION SF2)28This dictionary does not exist
in DANIEL. All particle informationis combined in diet.33.

PRODUCT PARTICLES (REACTION SF3)29This dictionary does not exist
in DANIEL. All particle informationis combined in diet.33.
30

PROCESS CODE
Additional: internal num.equivalent

PROCESS (REACTION SF3)

31

BRANCH CODES
Additional: internal num.equivalentMissing: free text explanations

BRANCH (REACTION SF5)32

PARAMETER CODES
Additional: internal num.equivalentMissing: free text explanations

PARAMETER (REACTION SF6)33

PARTICLES
Additional: 3 internal flags
Replaces all IBM particle dictionaries

PARTICLES CONSIDERED (REACTION SF7)

34

MODIFIERS
Additional: int.num.equiv.,int.flag
Missing: elaborate free text explan.

MODIFIERS (REACTION SF8)35

DATA TYPE

DATA-TYPE (REACTION SF9)36

QUANTITIES
Additional: 5 internal flags
Missing: expansions longer than 1 line
(desirable for some complicatedquantitiesjjfree text explanations/and group titles^-

QUANTITIES (REACTION SF5-SF8)

L-—--•—

37

RESULTRESULT
Missing: free text explanations

CINDA-QUANTITIES

42This dictionary does not exist in
DANIEL. CINDA quantities are given
in diet.12.

43

NLIB CODES FOR ENDF-6(Not needed for EXFOR/CINDA)
LIST OF DICTIONARIES

50(Not needed for EXFOR/CINDA)WP14
INFORMATION ABOUT RUSSIAN EVALUATED DATA.
l.BOFOD. Evaluatedphoto-neutron

data

library.

It includes

the (/',n),(y,n) and (y, fiss),(y,abs), (y,tot) cross section for 27
important elements. On the base of BOFOD the group constant systemis created.
Reference: Blokhin A.I. et al. Formation

andapplication ofevaluated photo-neutron data library. In:VANT,Ser.YK,1992,N3-4,p.3.
2.MENDL. The cross section library for study of transmutation
andactivationof materials

irradiatedby neutronsand protons

with energy up to 100 MeV. It contains neutron and proton reaction
cross sections for more than 500 stable and nonstable nuclei atthe energies from 1 to 100 MeV. Majorites of the data have beenobtainedby meansof geometry

dependent, hybrid

excitonmodel

taking into account preequi1ibrium a-particle emission.
Reference:

Konobeev

A.Yu.,

Korovin

Yu.A.,

Lunev

V.P.,

Masterov V.S., Shubin Yu.N.The cross section library for study oftransmutation andactivation

andenergy "until 100 Mev. In: VANT, Ser.YK, 1992,

protonswithof materials irradiated by neutrons

N 3-4,p.55.
3.ADL-3.
contains

Activation

20049 excitation

Data

Library,

versionfunctions of reactions

3. Thelibrary

on stable andunstable targets including isomer states. Cross sections for all
threshold
nuclearreactionsreactions

were

calculatedbystatisticaltheoryin the framework of Hauser-Feshbachofformalismwith contribution of non-statistical mechanism. Normalization ofcross-sections experimental data was used.
Reference:

Grudzevich O.T., Zelenetsky A.V., Ignatyuk A.V.,

Pashchenko A.B. "Catalog of ADL-3 library" In: VANT, Ser.YK, 1993,
N 3-4.
4.RDF-94. The Russian

Dosimetry

File (RDF-94)

It includes

46 reactions used in dosimetry and in measurements as standards.
11 reactions are taken from IRDF-90, 35 reactions evaluated in theCJD. Some evaluations were made using a generalized least squares
method. Covariance matrices were calculated and included into thefiles. Other evaluations were made using the excitation functions
systematics and calculations on theoretical models. In this casetheuncertainties

inseveralappropriate

energyintervals

aregiven.
The list of the CJD evaluations, included into RDF-94.
19-F(n,2n)51-V(n,«)63-Cu(n,^)

23-Na(n,^T)

52-Cr(n,2n)65-Cu(n,2n)

55-Mn(n,2n)89-Y(n,2n)45-Sc(n,2n)

55-Mn(n,3T)

90-Zr(n,2n)45-Sc(n,2n)m

54-Fe(n,2n)

93-Nb(n,n')m45-Sc(n,2n)g54-Fe(n,p)

93-Nb(n,2n)m

46-Ti(n,p)

56-Fe(n,p)

115-In(n,2n)

46-Ti(n,2n)59-Co(n,2n)127-I(n,2n)

47-Ti(n,x)

58-Ni(n,2n)

139-La(n,^)

48-Ti(n,x)

58-Ni(n,p)

141-Pr(n,2n)

48-Ti(n,p)

60-Ni(n,p)

181-Ta(n,^-)49-Ti(n,x)

63-Cu(n,2n)

197-Au(n,2n)24-Mg(n,p).

Reference:Manokhin V.N. et al.Russian Dosimetry File(RDF-94).
To be published in VANT,Ser.YK,1994 .
5. Atlas of photon energy-angularneutron interactions.

distributions

It contains 353 graphs

radiative capture processes. The

EXFOR

data

for

produced inabsorbtion andfor 52 elements andsome their isotopes were used in these publications.The comparisonof experimental andevaluation data from

BROND-2, ENDF/B-VI

wasperformed in some cases.
Reference: Blokhin A.I. et.al.Atlas of photon energy-angular
distributions produced in neutron interactions.

In: VANT, Ser.YK,

1993,N 2,p.
6. Belanova T.S.Evaluation of thermal neutron cross sections
andresonance integrals for isotopes of protactinium, americium,

curium and berklium. In: VANT, Ser.YK, 1993, N 1, p.22.

WP15

Memo CP-M/15

Date: 03.03.94
From: CDFE
Subject: Dictionary Correction and Additions.
To: Distribution

I would like to propose two changes in EXFOR Dictionary:1) with the aid to correct the clear incidental technical mistake theexplanations for two codes BRA and BRS in the Dictionary 34 must be
rearranged;2) because of the beginning-ifl- 1988 of the regular publication ofPreprints (Reports) of the Moscow State University Institute of Nuclear
Physics (which the CDFE uses for publication of various materials
concerned the photonuclear data evaluation) I support the appropriate
addition to the Dictionary 6.
Attachments:

Dictionary Correction and Additions-page 2.
Clearance: V.V.Varlamov

Distribution:
C.Duiiford,
H.Lemmel,O.Schwerer,
V.Mclane,
F.E.Chukreev,
V.N.Manokhin,

IAEA NDS
IAEA NDS
IAEA NDS

NNDC

CAJAD
CJD

N.Tubbs,
T.Tendow,
M.Chiba,Zhuang Youxiang,
Y.Kikuchi,
R.White,NEA-DB
RIKEN
JCPRG
CNDC
JAERI
USA LLNL NDG

Memo CP-M/15
Page 2

The following corrections should be made:DICTIONARY 34
BRA(BREMSSTRAHLUNG SPECTRUM AVERAGE) FOR PHOTONUCLEAR DATA

BRS
DATA

(AVERAGE OVER PART OF BREMSSTRAHLUNG SPECTRUM) FOR PHOTONUCLEAR

The following addition should be made:DICTIONARY 6
MSU-INP-MOSCOW STATE UNIVERSITY INSTITUTE"^ NUCLEAR 4RUSM0SPHYSICS. REPORTS

WP16
Present Status of JENDL Project
Yasuyuki Kikuchi
Nuclear Data Center
Japan Atomic Energy Research Institute
1. JENDL-3 revision 2 (JENDL-3.2)
The revision work of JENDL-3 has been almost completed. By adding new evaluationfor 16 nuclei, the evaluated data are given for 340 nuclei in JENDL-3.2. The Y~raY
production data are stored for 66 nuclei. About 180 nuclei out of 340 have a new or revised
data. Table 1 lists the nuclei and MAT numbers in JENDL-3.2. Table 2 summarizes main
modifications for JENDL-3.2.
For the natural elements, many parts of data were constructed from the data of theirisotopes. In the case where the resonance energy region are different from each other, theresonance regions are different even in the natural element data. In many cases, the data ofnatural element data are not consistent with those of isotopes. Since the natural elements
have many experimental data than isotopes, the data constructed from isotopes were modified
on the basis of those experimental data. Therefore, the users are recommended to use thedata of natural elements instead of those of isotopes.
The ENDF-6 format is adopted for JENDL-3.2. So their MAT numbers are changed tothe definition in the ENDF-6 format. In JENDL-3.1, data of some fission product nuclei arestored twice with different MAT numbers. It caused a confusion to the users. In JENDL3.2, double entries of data exist no longer. The double-differential data (DDX) are importantfor fusion neutronics. However, JENDL-3.2 in the ENDF-6 format adopts the conventional
MF4-MF5 representation of emitted neutron data instead of the MF6 format. We arepreparing a special purpose file, JENDL Fusion File, which provides the DDX data in theMF6 format for fusion neutronics.
For the convenience of users, the ENDF-5 format version will be available on request,
and pointwise data files will be provided, which are calculated at 0 K with RECENT or
RESENDD.
So far the middle of April 1994, re-evaluation of data for 19F, 150Sm, 152Sm and 154Sm
had not been finished. As to the y-ray production data, Ca and Pb were under re-evaluation.
JENDL-3.2 will be released May or June 1994.
Preliminary benchmark calculations have been made for important data. It has been
confirmed that the revised data of Fe are in very good agreement with measured integral data.
Data for main actinoids give better C/E values for fast and thermal reactor characteristics.
2. Future Subjects for JENDLJENDL-3.2 gives much better evaluated data than JENDL-3.1.
following problems are still existing:

However, theCovariance matrix
JENDL-3.2 has no covariance matrices. We recognize importance of the covariancematrices. A new working group has been organized in Japanese Nuclear Data Committee forstudy of evaluation method of the covariance matrices.
Energy Distributions
Energy distribution data in JENDL-3.2 should be reexamined. In particular, newrepresentation method proposed in the ENDF-6 format has not been adopted in JENDL-3.2.
So the energy balance is not always correct.
3. JENDL Special Purpose Files
The following evaluated data files other than JENDL-3.2 are being developed in Japan.
Their status is given below. No progress has been made for the (a,n) data file and the decay
data file.
JENDL Fusion FileJENDL Fusion File is made to provide precise double-differential neutron and charged
particle emission data by using MF6 representation of the ENDF-6 format. The evaluation
has been finished for the data of ^Al, Si, Ca, Ti, Cr, 55Mn, Fe, 59Co, Ni, Cu, 75As, Zr, 93Nb,
Mo, Sb, W, Pb and ^ B i , and is under way for 19F, Ge, Sn. SINCROS-II which consists of
GNASH, DWUCK, CASTHY and several auxiliary programs is used for the theoretical
calculation. Those results are examined by comparing with DDX measured at Tohoku andOsaka university. The data for JENDL Fusion File have been adopted in JENDL-3.2 after
approximately changing the MF6 representation to MF4-MF5 representation.
JENDL Actinoid File
This file will provide 89 nuclei mainly in the range above Z=90. The data for 57 nuclei
will be taken from JENDL-3.2. For the other nuclei, we need new evaluation. In the lastyear, the evaluation of 237Pu and 244Pu was made. At present, Dr. Konshin is investigating
the parameters for fission cross section calculation for other nuclei. By adopting his results,
new calculation will be made for other nuclides, and if needed the data taken from JENDL3.2 for some minor actinoids will be updated.
JENDL Dosimetry File
The first version of JENDL Dosimetry File was released in 1991 with the data for 61
reactions. In the last year, re-evaluation of several cross sections was made by members of
Dosimetry Integral Test Working Group of JNDC. New dosimetry reactions to be added to
the 61 reactions are also investigated. In the first version of JENDL Dosimetry File, thecovariance matrices were taken from other files such as IRDF-85. The evaluation of own
covariance matrices is also the subjects to this working group.
JFNDL Activation Cross Section File
The preliminary file has been compiled and its validation test started with integral datameasured at JAERI/FNS. The test shows that JENDL Activation Cross Section File gives themost preferable results among libraries tested. The test and revision of the preliminary fileis in progress.

JENDL High Energy Files
The evaluation of data for high energy neutrons and charged particles have been initiatedin JNDC. They will make data files for neutrons and protons up to 50 MeV and about 1.5
GeV. The former files will be used for the ESNTT project promoted in JAERI. The
evaluation of neutron data up to 50 MeV has been made for several structural materials.
However, the compilation of data files has not yet completed. The latter files will be used
for design of transmutation systems of high-level waste. The evaluation of data for Al, Pb
and Bi was made for proton induced reactions up to 1 GeV. The proton-induced reaction
data of Cr, Fe, Ni and Cu isotopes were also evaluated up to 15 MeV.
JENDL PKA/KERMA File
This file will store the spectra of primary knock-on atoms (PKA) and KERMA factors.
The data to be stored are created from the data files up to 50 MeV made for the ESNIT
project. A couple of codes to create the file have been developed and tested. However, thedata compilation work has not yet started.
JENDL Photonuclear Data File
The evaluation has been almost finished for C, N, O, Al, Cu, Bi and U in the y-ray
energy range up to 140 MeV. Their compilation in the ENDF-6 format is in progress. The
evaluation for Ti, Fe, Ta, W and Pb is also in progress.
A bibliographic index to the photonuclear data was published as JAERI-M 93-195.

Table 1 Nuclides and MAT numbers stored in JENDL-3.2

H- 1
Li- 6
B - 11
0-16
Mg-24
Si- 0
P-31
S -34

a-37
K-40
Ca-42
Ca-48
Ti-47
V-51
Cr-53
Fe-54
Co-59
Ni- 61
Cu- 63
Ga-71
Ge-73
Se-74
Se-79
Br-81
Kr- 83Rb- 85
Sr-88
Y-91
Zr- 92
Zr-96
Mo- 0
Mo-96
Mo-100
Ru-99
Ru-103
Rh-105
Pd-106Ag- 0
Cd- 0
Cd-111
Cd-116
Sn-114
Sn-118Sn-123
Sb-121

125
325
528
825
1225
1400
1525
1631
1731
1928
2031
2049
2228
2328
2434
2625
2725
2834
2925
3131
3234
3425
3440
3531
3640
3725
3837
3931
4031
4043
4200
4237
4249
4434
4446
4531
4637
4700
4800
4840
4855
5031
5043
5058
5125

H- 2
Li- 7
C - 12
F- 19
Mg-25
Si-28
S- 0
S -36
Ar-40
K-41
Ca-43
Sc-45
Ti-48
Cr- 0
Cr-54
Fe-56
Ni- 0
Ni- 62
Cu- 65
Ge- 0
Ge- 74
Se-76
Se-80
Kr- 78
Kr- 84Rb- 87
Sr- 89
Zr- 0
Zr-93
Nb-93
Mo- 92
Mo- 97
Tc- 99Ru-100
Ru-104
Pd-102
Pd-107
Ag-107
Cd-106
Cd-112
In-113
Sn-115
Sn-119Sn-124
Sb-123

128
328
625
925
1228
1425
1600
1637
1837
1931
2034
2125
2231
2400
2437
2631
2800
2837
2931
3200
3237
3431
3443
3625
3643
3731
3840
4000
4034
4125
4225
4240
4331
4437
4449
4625
4640
4725
4825
4843
4925
5034
5046
5061
5131

He- 3
Be- 9
N - 14Na- 23
Mg-26
Si-29
S-32
Cl- 0
K- 0
Ca- 0
Ca-44
Ti- 0
Ti-49
Cr-50
Mn-55
Fe-57
Ni-58
Ni- 64
Ga- 0
Ge- 70Ge-76
Se- 77Se- 82
Kr- 80Kr- 85
Sr- 86
Sr- 90Zr- 90Zr- 94Nb-94
M o - 94
Mo-98
Ru- 96
Ru-101
Ru-106
Pd-104
Pd-108
Ag-109
Cd-108
Cd-113
In-115
Sn-116
Sn-120Sn-126
Sb-124

225
425
725
1125
1231
1428
1625
1700
1900
2000
2037
2200
2234
2425
2525
2634
2825
2843
3100
3225
3243
3434
3449
3631
3646
3831
3843
4025
4037
4128
4231
4243
4425
4440
4455
4631
4643
4731
4831
4846
4931
5037
5049
5067
5134

He- 4
B - 10N - 15
Mg- 0
Al-27
Si-30
S -33
Cl-35
K-39
Ca-40
Ca-46
Ti-46
Ti-50
Cr-52
Fe- 0
Fe-58
Ni- 60Cu- 0
Ga- 69
Ge-72
As-75
Se- 78
Br-79
Kr- 82
Kr- 86
Sr- 87
Y-89
Zr-91
Zr-95
Nb-95
Mo-95
Mo-99
Ru- 98Ru-102
Rh-103
Pd-105
Pd-110Ag-llOm
Cd-110
Cd-114
Sn-112
Sn-117
Sn-122
Sb- 0
Sb-125

228
525
728
1200
1325
1431
1628
1725
1925
2025
2043
2225
2237
2431
2600
2637
2831
2900
3125
3231
3325
3437
3525
3637
3649
3834
3925
4028
4040
4131
4234
4246
4431
4443
4525
4634
4649
4735
4837
4849
5025
5040
5055
5100
5137

Te-1205225
Te-1255240
Te-129m 5253
1-131
5337
Xe-129 5440
Xe-133 5452
Cs-1335525
Cs-1375537
Ba-135 5640
Ba-1405655
Ce-141 5840
Pr-1435931
Nd-145 6034
Nd-150 6049
Pm-149 6155
Sm-149 6240
Sm-153 6252
Eu-1526328
Eu-1566340
Gd-156 6437
TT)-1596525
Hf-1777234
Ta-1817328
W -184 7437
Pb-2068231
Ra-2238825
Ac-225 8925
Th-2289028
Th-2339043
Pa-233
9137
U-235
9228
Np-236 9343
Pu-236
9428
Pu-241
9443
Am-242m 9547
Cm-241 9628
Cm-245 9640
Cm-249 9652
Cf-2499852
Cf-2549867

Te-122
Te-126
Te-130
Xe-124Xe-130
Xe-134
Cs-134Ba-130Ba-136
La-138Ce-142
Nd-142
Nd-146
Pm-147
Sm-144Sm-150Sm-154Eu-153
Gd-152
Gd-157
Hf- 0
Hf-178
W- 0
W-186
Pb-207
Ra-224
Ac-226
Th-229Th-234
U-232
U -236
Np-237
Pu-238
Pu-242
Am-243
Cm-242
Cm-246
Cm-250
Cf-250Es-254

5231
5243
5255
5425
5443
5455
5528
5625
5643
5725
5843
6025
6037
6149
6225
6243
6255
6331
6425
6440
7200
7237
7400
7443
8234
8828
8928
9031
9046
9219
9231
9346
9434
9446
9549
9631
9643
9655
9855
9914

Te-123Te-127m
1-127
Xe-126
Xe-131
Xe-135
Cs-135
Ba-132
Ba-137
La-139Ce-144
Nd-143
Nd-147
Pm-148
Sm-147
Sm-151
Eu- 0
Eu-154Gd-154Gd-158
Hf-174
Hf-179
W-182
Pb- 0
Pb-208
Ra-225
Ac-227TTi-230
Pa-231
U-233
U -237
Np-238
Pu-239Am-241
Am-244
Cm-243
Cm-247
Bk-249
Cf-251
Es-255

5234
5247
5325
5431
5446
5458
5531
5631
5646
5728
5849
6028
6040
6152
6234
6246
6300
6334
6431
6443
7225
7240
7431
8200
8237
8831
8931
9034
9131
9222
9234
9349
9437
9543
9552
9634
9646
9752
9858
9915

Te-124Te-1281-129
Xe-128
Xe-132
Xe-136
Cs-136
Ba-134Ba-138Ce-140Pr-141
Nd-144
Nd-148
Pm-148m
Sm-148
Sm-152
Eu-151
Eu-155
Gd-155
Gd-160
Hf-176
Hf-180W-183
Pb-204
Bi-209Ra-226
Th-227
Th-232
Pa-232
U-234
U -238
Np-239Pu-240
Am-242
Am-244m
Cm-244
Cm-248
Bk-250
Cf-252
Fm-255

5237
5249
5331
5437
5449
5461
5534
5637
5649
5837
5925
6031
6043
6153
6237
6249
6325
6337
6434
6449
7231
7243
7434
8225
8325
8834
9025
9040
9134
9225
9237
9352
9440
9546
9553
9637
9649
9755
9861
9936

Table 2 Main modifications for JENDL-3.2
C-12

capture cross section in 100 eV to 5 MeV, total above 8 MeV, someinelastic scattering cross sections
N-14
total cross section in 5 to 10 MeV, inelastic scattering cross sections
O
capture and inelastic scattering cross sections
Na-23
total cross section above 1 MeV
Al-27
inelastic scattering above 5.6 MeV, angular and energy distributions
Si
angular and energy distributions, small modification to inelastic
scattering cross sections
P-31
total cross section above 544 keVSAll cross sections above resonance region
K
total cross sections above 200 keV
Ca, Ti, V-51
almost all cross sections, angular and energy distributions, y production
dataCr
total cross section in 300 keV to 4 MeV, angular and energy
distributions of neutrons
Mn-55
part of inelastic scattering, angular and energy distributions
Fe
total cross section in 350 keV to 12 MeV, inelastic scattering crosssection, angular and energy distributions, y production data
Co-59
capture, inelastic scattering cross sections, angular and energy
distributions, y production dataNitotal cross section in 557 keV to 5 MeV, angular and energy
distributions, y production dataCu
cross sections in 50 to 153 keV, angular and energy distributions, yproduction data
Zr
Almost all data
Nb-93
resonance parameters, inelastic scattering, angular and energy
distributions
Mo
inelastic scattering, angular and energy distributions
Cd
resonance parameters, inelastic and capture cross sections
Sb
almost all cross sections, angular and energy distributions
Other Fission Products
resonance parameters, inelastic scattering and capture cross sections
Walmost all cross sections, angular and energy distributions
Pb
resonance parameters, almost all cross sections, angular and energy
distributions
U-233
resonance parameters, fission, inelastic scattering, (n,2n) reaction crosssections, fission spectrum
U-235
resolved and unresolved resonance parameters, fission spectrum, v p
U-238
resolved and unresolved resonance parameters, inelastic scattering crosssectionPu-239resolved resonance parameters, fission spectrum
Pu-241resolved resonance parameters

WP17

Status Report of JENDL Charged Particle Data
Yasuyuki KIKUCHI
Nuclear Data Center,
Japan Atomic Energy Research Institute,
Tokai-mura, Naka-gun, Ibaraki-ken, 319-11 Japan

1. Experimental Database
In order to use in the evaluation work of the charged particle and gamma-ray induced
nuclear data, the charged particles and gamma-ray induced experimental data storage andretrieval system (CHESTOR) has been developed by converting from EXFOR data. The
considered charged particles were proton, deuteron, triton, He-3 and alpha as well as gammaray.
The experimental data of thick target neutron and proton yields for proton and alphaparticle induced reactions on several elements were collected and stored in EXFOR format.
The considered elements were C, Al, Fe, Cu, W, Pb and U.
2. Evaluation of Data
The nuclear data of charged particle induced reactions were originally considered for
the JENDL High Energy File as well as neutron induced reactions. The lower energy data
are also evaluated, since JENDL does not have the charged particle induced data. Though
the charged particle spectra are not included in JENDL-3 General Purpose File, this problem
is solved in JENDL Fusion File.
The JENDL High Energy File considers only proton induced reactions as charged
particle reactions at this time. The results of proton-induced isotope production crosssections calculated by several codes were compared with each other as well as experimental
data. The considered codes were EGNASH, EXIFON, ALICE-F, ALICE/85, MCEXCITON,
NUCLEUS and HETC/3-STEP. It was found that the codes using statistical theory withpreeguilibrium correction could reproduce the experimental data of isotope production crosssections better than the others.
The proton nuclear data have been evaluated for Cr-50,52,53,54, Fe-54,56,57,58, Ni58,60,61,62,64, and Cu-63,65 up to 15 MeV mainly by using EGNASH-2 code. For the
proton optical potential parameter, Perey's and Walter-Guss's potential parameters werecombined. The (p,n) reaction is a main part of reaction, because of incident proton energy.
The evaluated results are almost in good agreement with the experimental data. The incident
energy will be expanded up to 50 MeV by using similar method.
The proton incident nuclear data up to 1 GeV have been calculated for Al, Pb and Bi
isotopes by using the ALICE-F code. These data are now under reviewing to be final
evaluated results.
3. Others
The primary knock-on atom (PKA) is produced through various nuclear reactions.
Estimation of PKA spectra is necessary to the KERMA factor calculation and the material
design applications, especially for the fusion application. ESPERANT code, which creates
the PKA/KERMA file from the evaluated nuclear data file, was developed. For the lighter

nuclei, it is difficult to create the PKA/KERMA file by using ESPERANT because of its
approximating limitation. Consequently, the SCINFUL/DDX code, which is modified fromthe detector response function calculation code, SCINFUL, is under development so as tocalculate both nuclear data and PKA spectra, simultaneously.
The calculation methods of charged particle stopping power were compared to estimate
its transportation in the actual materials and to calculate thick target yields. The preliminary
version of code calculating thick target yields of neutron emission from the evaluated nuclear
data files was developed.
The (a,n) reaction data for several nuclei have been evaluated to check the criticality
and heating safety of storing spent fuel. The data related to fusion reactions were researched.
The reaction channels and reaction rates for nuclear fusion are investigating to perform an
plasma analysis with measuring the fusion products.

WP18
PRESENT STATUS OF
PHOTONUCLEAR DATA EVALUATION AT JAERI
Yasuyuki Kikuchi and Norio Kishida
Department of Reactor Engineering
Tokai Research Establishment
Japan Atomic Energy Research InstituteTokai-mura, Naka-gun, Ibaraki-ken

Photonuclear cross sections are required in several areas, e.g., electron accelerator shielding, radiation therapy and nucle,ar transmutation of radio active wastes.
A Photo-Reaction Data Working Group was organized as one of working groups of
the Japanese Nuclear Data Committee (JNDC) in 1989 in order to evaluate photonuclear reaction cross sections. Various kinds of photonuclear cross sections havebeen being evaluated. Photonuclear data of all natural isotopes, several transuranic
nuclides and some fission products will be evaluated to the end of 1990's. We do
not have sufficient experimental data necessary for the evaluation and hence we areproceeding the evaluation work with the help of theoretical calculation based on
the statistical nuclear reaction models.
Untill now we have evaluated the photonuclear data for D, 12C, 14N, 16 O,
23Na, 24,25,26 Mg) 2 7 ^ 28,29,30^ 4 0 , 4 8 ^ 46,48 Ti) 5 2 ^ 5 4 ^ 5 9 ^ 58,60 Ni? 63,65 C l l )Zr, 92,94,96,98,100MO) lSl-J^ 197A u ? 206,207,208pb? 209 B i ^235,238^ T h e f o U o w i n g

90photonuclear cross sections are evaluated: photonuclear absorption cross sections
not to include elastic cross sections, photoneutron cross sections, photoproton crosssections, yield cross sections for photoneutrons, photoprotons, photodeuterons, phototritons, photo-3He-particles and photo-alpha-particles, single neutron emission
cross sections, double neutron emission cross sections, energy spectra, angular distributions and DDX for photoneutrons and photoprotons, and nuclide production
cross sections. The maximum energy of incident photons is 140 MeV because theevaluation work becomes very hard once the pion production channel opens. The
evaluated photonuclear data file is constructed using ENDF—6 format. The firstversion of the evaluated file will have been completed by next April.
Joint evaluation work between JAERI JNDC and MSUINP CDFE (Moscow
State University, Institute of Nuclear Physics, Centre for Photonuclear Experiments
Data) may be carried out within the following limits. First, CDFE evaluates theexperimental photoabsorption and photoneutron crosss sections using the data reduction method developed by CDFE. On the other, JNDC performs theoreticalevaluation for particle emission cross sections, nuclide production cross sections,particle energy spectra, etc. based upon the photonuclear cross sections evaluatedby CDFE and makes the evaluated photonuclear data file.

WP19
The Activities On Neutron Reaction Data At CNDC
Liang Qichang

Zhuang Youxiang

Chinese Nuclear Data Center
China Institute of Atomic Energy
P.O.BOX 275(41),Beijing,102413
P.R.China

1. EXFORIn the period from May 1992 through December 1993, CNDC has compiled
61 entries for neutron reaction data measured in China, besides, another4 entries have been corrected, all of these have been sent to IAEA/NDS
with diskettes as follows:
No. of transmission
diskette
TRANS 3002
TRANS 3003
TRANS 3004
TRANS 3005
TRANS 3006
TRANS 3007
RE-TRANS 3001

number of entries
contained
7
22
13
7
7
5
4

date oftransmission
18-05-92
14-08-92
08-06-93
08-06-93
06-08-93
07-12-93
07-12-93

The EXFOR master libray from NDS and related codes for EXFOR dataprocessing and checking as well as the database storage and retrieval
system from NNDC were operated on micro-VAX-2, and the EXFOR data canbe accessed on computer directly.
The ERES code for EXFOR data compilation completed by ourselves
recently and ANDEX code for the same purpose from NDS have been put into operation on PC-386.
2. EVALUATED NEUTRON REACTION DATA(1). CENDL-2
A lot of efforts was spent in order to complete the CENDL-2 inpast two years, it was finally completed and released in the early of
1993. 53 nuclides in total contained in the library were checked by the
ENDF utility codes.
The description of evaluations in CENDL-2 were published in INDC
(CPR)-025/L(1991) and INDC(CPR)-028/L(1992).
(2). Related Codes For Library Management
In order to manage the evaluated nuclear data library, the utility
codes,version 6.8, and the data base storage and retrieval system from
NNDC were put into operation on micro-VAX-2.
Now some of the main libraries for evaluated neutron reaction data
including CENDL-2, ENDF/B-6, JENDL-3 and BROND-2 have been loaded indisks of micro-VAX-2 and can be accessed on computer directly.

3. MODEL THEORY CODES FOR NUCLEAR DATA CALCULATIONIn recent two years, several model theory codes have been developed
perfected and replanted by CNDC and its coordination network.
FMT (Zhang Jingshang)
Based on the unified Hauser-Feshbach and exciton model, the FMT
code, a special version of UNF, for calculation of neutron induced reaction on fissile nuclides at incident energy up to 20 MeV has been developed and used in the evaluation of U-238.
RAC92 (Chen Zhenpeng et al.)
A comprehensive R-matrix analysis code based on multi-channel andmulti-level R-matrix theory has been developed and used to analyse then+B-lo system.
CFUP1 (Cai Chonghai and Shen Qingbiao)
A code for calculation of charged particle as well as neutron induced reaction on fissile nuclei at energy region up to 35 MeV, including 1-5 particles emission has been developed and used to calculate
p+Am-241 and p+U-235 systems,the incident energy from 4 to 35 MeV.
SPEC (Shen Qingbiao and Zhang Jingshang)SPEC is a code for calculating cross section and spectra of neutronor charged particles(p,d,t,He-3,alpha) induced reactions on medium-heavy
nuclei in incident energy up to 60 MeV.
DDCS (Shen Qingbiao)
DDCS is a code for calculating nucleon and composite double differential cross section of the neutron or charged particles(p,d,t,He-3,
alpha) induced reactions in energy region up to 50-100 MeV.
Besides, some useful codes,such as ECIS79, SAMMY, DWUCK, ALICE and
GNASH etc., obtained from abroad have been or are being transplanted on
our computer, some of them have been used in evaluation.
4. CODES FOR NUCLEAR DATA PROCESSING AND PLOTTING
In the past two years, several codes for nuclear data processing
and plotting have been completed by CNDC.
DDXB1 (Zhang Jin and Liu Tong)
This code can be used to produce n, p and alpha particles total
emission spectra integrated over angles in c m . system or total spectra
at given angle in lab. system from MF6 in ENDF/B format.
MAINPLT (Liu Tong and Zhao Zhixiang)
This code can be used to process and plot the evaluated cross sections data(MF3) and angular distribution data(MF4) in ENDF/B format and
EXFOR data.
CODE SYSTEM FOR INTERCOMPARISON (Liu Tingjin and Sun Zhengjun)This code system can automatically retrieve and plot the evaluateddata and EXFOR data in batches mode, this code system can deal with thecomparison of cross section, DA, DE and DDX data among several evaluateddata and experimental data.

5. WORK IN PROGRESS
We are now preparing the CENDL-2.1, it will contain correction to
known errors such as the modification of energy spectra etc., some renewal evaluations and a few new evaluations, about 68 nuclides will becontained in this version.
The main changes in this version are as follows:(1). Benchmark Testing
Benchmark calculation for CENDL-2 has been begun. This work wasdelayed by lack of manpower and appropriate computer, now a SUN-10 work
station has been installed in CNDC and connected with micro-VAX-2, sosome preliminary results are expected in the near future.
(2). Re-evaluation For BE-9, CA-nat, U-238
The re-evaluation of neutron data for Be-9, Ca-nat and U-238 arecarrying out by using new model theory codes, in addition to the crosssections, angular distributions will be re-evaluated, the double differential cross section, gamma production data, as well as covariancedata will be added in the data files.
Besides, most of the evaluations in CENDL-2 will be supplemented
with the gamma production data file.
(3). New Evaluations For Some Nuclides
A. The new evaluations for Ag-nat, Al-27, Co-59, Fe-nat,54,57,58
Mn-55, Cr-nat,50,52,53,54, Cu-nat,63,65 and Nb-93 will be containedin CENDL-2.1, they are the joint Chinese/Japanese evaluations completed
in JAERI/NDC in 1992, among them, the Fe-54,57,58, Cr-50,52,53,54 andCu-63,65 are new evaluations for CENDL-2.1, and the others will supersed
the old one in CENDL-2 due to the consistent reasons for natural Ag, Fe,
Cr and Cu or more complete data files(including gamma production data)
are given for Al-27, Co-59, Mn-55 and Nb-93.
B. The new evaluations for Fe-56, Mg, Tl, Lu, Ga and Cl havebeen basically completed by using UNF code in CNDC and its coordination
network recently, these evaluations contain the data of MF1-6 andMF12-15, for the Fe-56, the uncertainty files for cross sections,angular distribution and double differential cross section are also
given.

WE20
Charged-Particle and Photonuclear Data Activities
at CNDC
Zhuang Youxiang

Liang Qichang

1. Compilation
During 1993-1994 the 14 entries of S0010, S0026-S0038
measured in China have been compiled and sent to the
IAEA. The other 12 data sets measured in China are being
compiled and will be submit to the IAEA.
2. Evaluation and Calculation
The evaluations and calculations of intermediate energy
nuclear data for Fe-56, Cu-63 and Cu-65(p,n) monitor
reactions have been carried out in incident energies up
to 1200 MeV, 11500 MeV and 1820 MeV, respactively. It is
supported by the IAEA.
The evaluations and calculations of photonuclear datainduced on Al-27, Fe-54 and Bi-209 have been accomplished. They were calculated by means of theoretical code
GUNF.
3. Theoretical code
The code GUNF established by ourselves can calculate
photonuclear data in ENDF/B-6 format of files 3, 4 and6 with the approximate incident energies up to 30 MeV,
including the scattering, absorption and particle productions.
We would like to make more contributions to the IAEA
with CRP or RCP according to the data needs for application.

WP21
Memo

CNDC-25/04/94-002

To:
Participants
From: Liang Qichang
Subject: A matters on Chinese EXFOR neutron data compilation
CNDC has taken over the responsibility of compiling
Chinese EXFOR data under a research contract in the past
several years due to the vacancy of post for EXFOR compilation in NDS. Since then we have compiled 70 EXFOR entries
in which almost all recent neutron reaction data measured
in China were included.
Now, the EXFOR compilation in NDS has been continued
when Dr. H.Wienke was hired. So my questions on this subject
are:1. Does CNDC continue responsible for Chinese EXFOR neutron
data compilation, since there are some duplicate compilation in NDS and CNDC in the past two years.
2. If so, CNDC would like to continue responsible for thismatter. Is CNDC responsible for EXFOR compilation forliteratures in both Chinese and English language or only
for Chinese language literature.

Memo
To:
From:

CNDC-25/04/94-003

Participants
Liang Qichang

Subject: Proposal to IAEA for EXFOR data and ENDF datatransmisson
Since CNDC has adopted the NNDC VAX EXFOR and ENDF
data base system, the EXFOR master library from NDS andthe main libraries for evaluated neutron reaction data
have been loaded in disks of micro-AVX-2 and can be accessedon computer directly, so my proposal to IAEA are:1. IAEA send CNDC the supplement EXFOR data periodically,for example, IAEA has sent CNDC the EXFOR master libraryin the middle of 1992, it is expected that IAEA send CNDC
the supplement EXFOR data(new entries entered into Vienna
master library from 30 June 1992 to 1 July 1994) in themode of LB***.TLB and RED.LB*
2. IAEA send CNDC in time the update version of the main
libraries for evaluated neutron reaction data, for example
we want to have the JEF-2, ENDF/B-6.2, BROND-2.1 and
IRDF(90) recently.

Memo CNDC-25/04/94-<W
To:

Participants

From: Zhang Jingshang

Zhao Zhixiang

Subject: A problem on the double differential cross sections(DDX) represented by using Legendre coefficients inlaboratory system in ENDF/B-6 format.
For more detial please to see separate article:
Zhang Jingshang Zhao Zhixiang, The forbidden angularregion of secondary particle emission in the laboratory system, INDC(CPR)-030/L, p.17(1993).

WP22
From:
SMTP%"@sequent.kiae.su,@cajad.uucp:chukreev@cajad.kiae.su"
4:15:24.55
To:
TUBBS
CC:
Subj:
MEMO A/65

23-MAR-1994 1

To:manokhin@cjd.fei. Obninsk. SU/ NNDCVM@BNL.GOV, RNDS6IAEA1.BITNET,
Tubbs@NEA.FR, varlamov@compnet.msu.su
Message-Id: <ACFY3ajuMB@cajad.kiae.su>
O r g a n i z a t i o n : Nuclear S t r u c t u r e and Reaction Data Center
From: Chukreev F . E . <chukreev@cajad.kiae.su>
Date: Wed, 23 Mar 94 15:39:43 +0300
X-Mailer: BML [MS/DOS Beauty Mail v.1.36]
S u b j e c t : MEMO A/65
Lines: 4 9
MEMO CP-A/65

To:
Distribution
From:
F.E . Chukreev, V.V.Varlamov
Subject: Some remarks on old and not correct data in B-, L-TRANSes.
There are well known problem of needs of recompilation of
the old and not correct data.
We would like to discuss two examples of situation that can
not be estimated as normal:
1. "The Munzel data-situation"
Let us see B0002007. The code "SUM" have been used for keyword
REACTION. This code is obsolete now. Who must correct this SUBEN-T?
This correction is needed because searching codes do not "know"
SUM. Similar examples are numerous.
2. The problem of not correct SUBENT records for somephotonuclear reaction channels when several reactions could
occure in the same energy region.
Let us discuss one example only for which we selected
L0039037 subentry. This SUBENT has REACTION:(20-CA-40(G,N)20-CA-39, ,SIG)
These data were measured for 15.37 - 29.47 energy region,
where not only (G,N) but (G,N+P) reaction is possible also.
The data from L0039037 are very similar to ones from
Forkman and Peterssen review (see p.676 of Handbook on Nuclear
Activation Data), where REACTION is:(G,N) + (G,PN) .
Authors of L0039037 have measured the summed (G,N)+(G,PN)
cross section
c e r t a i n l y but t h i s curcumstance does not r e f l e c t e dby SUBENT records!
We could continue similar examples.
Therefore we would l i k e to discuss t h i s problem during t onearest NRDC Meeting. The main questions on t h i s subject a r e :1. I s the problem of recompilation of such kind of
data
actual now?
2. Who could be responsible for such job?
F.E.Chukreev, V.V.Varlamov
Distribution:
C.Dunford, IAEA
N.Tubbs, NEA-DB
V.N.Manokhin, CJD
F.E.Chukreev, CAJAD
V.Varlamov, CDFE
V.McLane, NNDC
M.Chiba, JCPRG
Zhang Jingshang, IAE-CP
T. Tendow, RIKENWP23

THE CURRENT STATUS OF CENDL-2

Zhang Jingshang
Chinese Nuclear Data Center
P.O.Box 275(41)Beijing 102413 China(0086)9357275

Liu Tingjin
Chinese Nuclear Data Center
P.O.Box 275(41)Beijing 102413 China(0086)9357729

ABSTRACTThe Version 2 of Chinese Evaluated Nuclear
Data Library (CENDL-2) was completed andworldwide released in 1992 u . It contains evaluated neutron reaction data of 54 elements or
isotopes from 1-H-l to 98-Cf-249 in theneutron energy range from 10~5 eV to 20 MeV in
E N D F / B - 6 format. Most of elements or
isotopes have files 1—5, some important isotopes
have double differential cross section (file6), y-production data (files 12-15) andcovariance data (file 33). For use of this library a
set of computer codes have been established,which are available on magnetic tapes from
IAEA. Based on the requirement and thefeedback information, the working plan on improvement and development to CENDL—2 hasbeen worked out. Herein the further development of CENDL-2 and the current status arepresented.

Zhao Zhixiang
Chinese Nuclear Data Center
P.O.Box 275(41)Beijing 102413 China(0086)9357830

elements or isotopes in CENDL—2 have better
evaluated cross sections data than others sincemore new experimental data were used during
CENDL—2 evaluation period, meanwhile theanalysis processing and the parameter adjustment in the calculation were performed more
carefully. An example is shown in Fig.l for the
cross section of 7Li inelastic scattering to thesecond level (4.63 MeV). However, surveying
CENDL-2, it can be seen that the files and elements in the library are still not more enough topractical application, it needs to add more elements or isotopes and more files (y-production
data, double differential cross section anduncertainties).

I . Intercomparison and Benchmark Test
To appraise CENDL—2, the intercomparisons with "Large Evaluated Files" such as
ENDF/B-6, JENDL-3 and BROND-2 andsome benchmark tests have been performed.
1) The cross sections of 38 elements or
isotopes from CENDL—2 have been comparedwith those of E N D F / B - 6 , JENDL-3 andBROND—2. It was foupd that about two third ofE(MeV)
Fig.l Cross section of 7Li inelastic
scattering to 4.63 MeV
2) With the Cooperation of Russian Nuclc-

ar Data Center, the intercomparison of
CENDL-2 with BROND-2 as well as
JENDL-3, ENDF / B-6 for Fe, Ni, Cr neutron
reaction data have been done 3. The results indicate that
® There are considerable discrepancies forsome threshold reaction cross sections, an example is shown in Fig.2 for the cross section ofNi(n,ot) reaction.
(D There are systematical deviations in thesecondary neutron emission spectra of (n,nO,(n,2n), (n.n'p), (n.n'oc), etc. and their total
neutron emission spectra: the low energy
neutrons ( less than several keV ) have higher
values in E N D F / B - 6 , then that in JENDL-3,
BROND-2, while are missed in CENDL-2. Anexample is shown in Fig. 3.
® For total cross sections, the high resolution data are given in ENDF / B-6, JENDL-3(modified recently), but the data in CENDL-2
and BROND-2 is lower and the " smoothregion" is too wide.
© The shapes of the elastic differential
cross section are quite different for some incident
neutron energies.

isotopes were intercompared, most of which are
fission products. It was found that the better data are 25 from JENDL-3, 13 from E N D F / B-6
and 3 from BROND-2 (to see table 1 ). However, IO3Rh, 145Nd data of all libraries are not inagreement
withexperimental
data
and 164Dy, 176Lu data only existed in
ENDF/B—6 and are very old ( taken fromENDF / B—3 ). As an example, the total crosssection of 103Rh is shown in Fig.4 . The large
discrepancies have been found in the three libraries for some threshold reactions and for capture
cross sections of many elements, which are havenot any experimental data.

Fig.3 Secondary neutron spectrumof Ni at 14.1 McVTable 1 The intercomparcd isotopes
and the libraries with better data
Isotopes

Library

E(MeV)
Fig.2 Ni(n,a) cross section
3) To meet the needs of users andbenchmark test, more elements or isotopes need
to be supplemented in CENDL—2. For this purpose, in the first stage the data from
ENDF/B-6, JENDL-3 and BROND-2 of 41| 233,234^ 2 4 3 C m ) « 3 K r ) .03. lOS R h > . 3 1 . 1 3 5 ^JENDL-3|!

l33 n4 135- 'Cs, I4J Nd, l47-"•• i a - p m ,.47, 149. ISO, I5l,152g m
231,24l,242

ENDF / B-6

154, 155. 156,157, I S 8 Q j

Pu, IM U, "153, " • . 155j7

BROND-2

Am242/-.

242m. 243

thermal benchmark assemblies were calculated
by using the microscopic data from CENDL-2,
and for comparison purpose, also fromE N D F / B - 6 , JENDL-3 and JEF-1. Someprimary results have been obtained, which guidethe improvement of CENDL—2.

4) Using code system NSLINK for
raultigroup constant generation, which were obtained from NEA Data Bank and installed on
working station MIPS at CIAE, and code system
PASC—1 for reactor physics calculation, which
was modified, the group constants were generated and some integral quantities for some fast,F=—'

f~T i i iii[

1—i

1 II

|*i. m i |

TTT

Oi=L
ftooi

0-1

0. 01

E(McV)
Fig.4 Total cross section of !03Rh
II. The Development of CENDL-2
Based on the intercomparison, benchmark
test mentioned above, and the feedback information by users, CENDL—2 has been and is being
improved.
1) Rc-cvaluation and updating

The neutron reaction data of 238 U, 9Bc, andCa have been re-evaluated based on more newexperimental data and new calculation by using
FMT, UNF 4 codes developed at CNDC forfission nucleus and structural materials,
respectively. Taking 238U data as an example,
the data arc much improved5 : Files 6, 12 - 15
arc supplemented; the cross sections of total anddiscrete level inelastic scattering were re—cvalu-

ated. The contributions from direct inelastic scattering were calculated by using coupled-channel
optical model code CCOM for low levels, andcode DWUCK for high levels.
In addition, the evaluations for elements
Ag, Al, Fe, Cr, Cu, Co were completed by
Chinese scientist at JNDC cooperated withJapanese partner. The comparisons of these datawith those in CENDL-2 have been done. They
will be adopted in CENDL-2.
2) New evaluation and supplement
The data of "Fe, Hg, Tl, Lu, Ga and Cl
have been evaluated at CNDC and CNDN (Chinese Nuclear Data Network ). The purposeof the evaluation of ^ e is not only to provide
high quality evaluated data but also to test UNF
code. Obvious improvement are obtained. As an
example the DDX of (n,xa) is shown in Fig. 5.
There are no or only very old data for other 5 elements in E N D F / B - 6 , JENDL-3 andBROND-2 libraries, so it should be updated or
supplemented. So far the data of 15 elements or
isotopes have been evaluated and will be supplemented in CENDL-2.

To solve the problems found through theintercomparison described above, some modifications for CENDL—2 are being performed.
(D Neutron spectrum modification
As mentioned above, the secondary neutron
spectra in low energy less than several keV calculated with code MUP—2 arc missed. This isprobably caused by the technical reason in thecode. It is very difficult to re—calculate thespectra again. A method is being studied, andwill be used to modified these neutron spectra in
CENDL-2.
© Total cross section updating
Through the intercomparison, it is foundthat many structures in the total cross sections ofsome structural material are missed, and the energy points are too rare. These data will be replaced by high resolution experimental data orother high quality evaluated data.
d> Adding y-production data
A feasible semi-empirical method is being
studied to calculate y—production and will be
used to add y-production data to CENDL-2 forsome element or isotopes, which are important
for application.
4) Further improvement of CENDL-2:
Evaluation

ENOF/B-6
1
'?*%i

0.1

E
0.01

•

s79
EIN = 11.8 MEV.
90 Oegree

*X
\
11 [
I

8

10

12

MeV
Fifc.5 DDX of ^FeCn.xoc) at 90
3) Modification and improvement•

16

More evaluations have been arranged, andarc being performed at CNDC and CNDN.
® The neutron reaction data for natural Ni
and its isotopes ( 38>60-6I-a- M Ni ) are being evaluated. To improve CENDL-2 and meet theneeds of the international fusion research, theevaluated data will include double differential
cross sections and be consistent between natural
one and it's isotopes.
© The evaluations and calculations ofneutron data for fission products arc being studied. Especially, the U 5 Nd, 164Dy, 176Lu data
are being evaluated, since for these isotopes theexisting data in the current large evaluated libraries are discrepant with new experimental data or
arc very old.
® With the cooperation of Russian Nude-ar Data Center, the threshold reaction cross sections of natural Fe, Cr, Ni and their isotopes arebeing evaluated or re—evaluated. The best one
would be recommended.

5) Further improvement of CENDL—2:
Measurement
To solve the severe discrepancies, somemeasurements have been and are being performed.
® DDX on Li, Be, B, C, Bi at 14 MeV and
6-13 MeV by means of TOF method on
Cockcroft Walton and Tandum accelerators6 at
CIAE;® (n,x) reaction cross sections, angular distributions including^Cafoa), 58Ni(n,a)7 at
neutronenergy4-6
MeV
with
gridded—ionization chamber on Van de Graff at
Beijing University, and 93Nb(n,ap) ( also DDX )at 14.6 MeV with nultitelescope system on
Cockcroft Walton accelerator8 at China Sci. andTech. University ( Fe, Cr, Ni(n,p), (n,xa) in future ).
(D The activation cross sections of many
isotopes, especially those leading to long—lived
radio—nucleus, have been measured at CIAE9,
Lanzhou10, Sichuan11 andBeijing
Universities12 with Cockcroft Walton. Van deGraff and Tandum.
© When CENDL-2.1 is finished, themacroscopic quantities for some fast, thermalbenchmark assemblies and also for "broomstick"experiments will be calculated again for the integral testing. Some macroscopic measurements on
Cockroft Walton accelerator at CIAE are being
prepared. At first, the transmutation spectra ofneutrons through structural material sphere or
slab will be measured.
Ill. Methodology and Codes for Improvement of C E N D L - 2
The improvement of CENDL-2 is closely
related to the progress on methodology and codedeveloping. In recent two years the researches on
evaluation methodology and codes for nuclear
data calculation, plotting and processing havebeen carried out.
1) Evaluation methodology
For the evaluations of averaged resonanceparameters, especially the average level spacing,a method based on Bayesian approach for correcting the energy level missing has been established. The covariance files also are studied. A
simple method to evaluate covariance file for
DDX has been developed and applied to ^Feevaluation. Impacts of negative and distant level
on resonance cross sections have been studied
and analysis codes developed. A simultaneous
evaluation method for correlated data are developed and used to the cross sections of ^238
U(n,f), ™U(n,y),c r ^ U ) / ^ U ) and c
2) Codes for calculating nuclear reactiondata
In recent two years, several theoretical model codes have been developed, perfected andreplanted for nuclear data calculations. UNF isdeveloped for structural materials, FMT is used
for fission nucleus, RAC92 is a comprehensive
R—matrix
analysis
code
based
oi
multi—channel and multi—level R—matrix theory, CFUP1 is for calculating charged particle aswell as neutron induced reaction of fission nuclei
at energy region up to 35 MeV, SPEC is a codefor calculating cross sections and spectra ofneutron or charged particle induced reactions
with in incident energy up to 60 MeV, DDCS isfor calculating nucleon and composite double
differential cross sections of the neutron or charged particles( p, d, t, 3He, a) induced reactions inenergy region up to 50—100 MeV.
3) Codes for Nuclear Data Processing and!
Plotting
DDXB1 is used to produce n, p and a parti
clc total emission spectra in c.m.s or total spcctizi
at given angle in Lab. system from File 6 m

ENDF / B format, MAINPLT is used to process
and plot the evaluated cross section and angular
distribution in ENDF / B format and EXFOR
data. Intercomparison code system ICPL can retrieve evaluated data and EXFOR data and process them for plotting out the figure to show thecomparison among several evaluated and measured data in batches. EXFOR Library and Related Software: for making evaluation more convenient, the EXFOR data master library has
been installed in hard-disk of MICRO VAX-II
computer at CNDC. Related storage andretrieval system are replanted and provided tousers.
4) Chinese Evaluated Nuclear Parameters
Library (CENPL)
To provide evaluators input data for nuclear
data calculation and make evaluation more convenient, the CENPL is being established. The
CENPL consists of data files and retrieval code
system. So far six sub—libraries are included in
CENPL—1: MCC ( Atomic masses and characteristic constants for nuclear ground states );DLS ( Discrete level schemes and branch ratiosof y decay ); LDL ( Level density parameters );GDP ( Giant dipole resonance parameters for
y—ray strength function ); FBP ( Fission barrierparameters); OMP ( Optical model parameters).

IV. Conclusion Remarks
The most of works on the evaluation andmeasurements mentioned above have been or are
being done. Exactly, the items 1)—3) will be finished in this year, the item 4) will be finished in
one or two years and the item 5) will be
continuously done to get new results.
After finishing items 1)—3), CENDL-2.1
will be established and will be released by the endof this year. CENDL—2.1 will include evaluatedneutron reaction data of 68 elements or isotopes,of which 15 isotopes arc new evaluated and added, 9 isotopes arc re-cvaluatcd and updated,most of other data will be modified and improved. Furthermore, more y-production data,

double differential cross sections and covariancedata are included.
Since CENDL-2 was finished, great efforts
have been made at CNDC and CNDN to improve CENDL-2. The development of
CENDL—2 have been made in three aspects : increasing the number of nuclides, extending files
and improving quality. After CENDL—2.1 iscompleted, the further evaluations andmeasurements will be continuously going on todevelop reaction nuclear data.
Acknowledgments
The authors and also CNDC, would like toexpress the appreciation to NDS / IAEA for
their great support in developing CENDL andoffering EXFOR master file and many evaluateddata, to NNDC/USA for giving E N D F / B-6
data and ENDF / B, EXFOR program systems,
to JNDC/Japan for the offering benefit
cooperation to Chinese scientists performing theevaluations in JNDC and providing programs,
to CJD/IPPE of Russia for the benefit
cooperationonintercomparison,to
NDB / NEA for their offering many programs.
References
1. Liu Tingjin et al., "CENDL-2, Chinese Evaluated Nuclear Data Library, Version 2," Proc. ofConference on Nuclear Data for Sci Tech., Julich,
May. 1991, p804
Liang Qichang et al., "Chinese EvaluatedNuclearData
Library
Version2,"
IAEA-DNS-61 (1992)
2. IAEA-NDS-107 Rev.6 June 1992
3. Liu Tingjin et al., "Intcrcomparison of Fc, Cr,
Ni Neutron Data from CENDL-2, BROND-2,
and ENDF/B-6, JENDL-3 Libraries," Proc.
of Conference on Nuclear Data for Sci Tech.,
Gatlinburg,USA(\994) (to be published)
4. Zhang

Jingshang,"A

UnifiedHauser—Feshbach and Exciton Model for Calculating Double Differential Cross Sections of
Neutron Induced Reactions Below 20 MeV,"
Nucl. Sci. Eng. 114,55 (1993)
5. Tang Guoyou et al., "Revision on Recommended Data for CENDL-2 in 1993 Version,"
Communication of Nuclear Data Progress 10,
171(1993)
6. Shen Guanren et al., "Measurement of Secondary Neutron Double Differential Cross Section from ^ B i at 14.2 MeV," Chinese J. Nucl.
PAysics,14,234(1992), "Measurement of Secondary Neutron Spectra from 6>7Li Induced by
14.2 MeV Neutrons," 15,367(1993)
7. Tang Guoyou et al., "Measurement of Cross
Section at 5 MeV and Angular Distribution at 4
and 5 MeV for reaction of *Ca(n,a) 37Ar,"
CommunicationofNuclear
Data
Progress,S,l(1992),CNDP,10,\4(l993)
8. Ye

Bangjiaoetal.,"DevelopmentofaMultielescope System for the Measurement ofDifferential Cross Sections (n,Charge Particle)
Reaction/ Communication of Nuclear Data Progress, 10,19(1993) Thesis, Univ. of Sci. & Tech.
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9. Zhao Wenrong et al., "Investigation of the
Cross Section for 89Zr(n,ocn) reaction," Chinese
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10. Wang Yongchang et al., "Recent Progresson 14 MeV Neutron Activation Cross Section
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11. Peng Xiufeng et al., "Measurement of
Excitation Function for Reactions 107Ag(a,nX
107
Ag(a,2n) and 109Ag(a,2n),* Communicationof Nuclear Data Progress, 8, 19(1992)
12. Tang Guoyou et al., "Cross section
Measurement of MZn(n,p) MCu Reaction from4 to 7 MeV," Communication of Nuclear Data
Progress, 11 (1994) (to be published )

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