Image1.gif (2185 bytes) INTERNATIONAL ATOMIC ENERGY AGENCY

NUCLEAR DATA SERVICES

DOCUMENTATION SERIES OF THE IAEA NUCLEAR DATA SECTION

IAEA-NDS-175
Rev. 3, October 1998

 

 

 

FENDL/E-2.0
Evaluated nuclear data library of neutron-nucleus interaction
cross sections and photon production cross sections and photon-atom interaction cross sections for fusion applications

Released on May 15, 1998

Summary documentation
by
A.B. Pashchenko and H. Wienke

 

 

 

Abstract: This document presents the description of a physical tape containing the basic evaluated nuclear data library of neutron-nucleus interaction cross sections, photon production cross sections and photon-atom interaction cross sections for fusion applications. It is part of the evaluated nuclear data library for fusion applications FENDL-2. The data are available cost-free from the Nuclear Data Section upon request. The data can also be retrieved by the user via online access through international computer networks.

 

 

Nuclear Data Section
International Atomic Energy Agency
P.O. Box 100
A-1400 Vienna
Austria

e-mail: services@iaeand.iaea.org
fax: (43-1) 20607
cable: INATOM VIENNA
telex: 1-12645
telephone: (43-1) 2060-21710

Online: TELNET or FTP: iaeand.iaea.org
username: IAEANDS for interactive Nuclear Data Information System
usernames: ANONYMOUS for FTP file transfer;
           FENDL2 for FTP file transfer of FENDL-2.0;
           RIPL for FTP file transfer of RIPL
Web: http://www-nds.iaea.org

 

 

Note:

The IAEA-NDS-reports should not be considered as formal publications. When a nuclear data library is sent out by the IAEA Nuclear Data Section, it will be accompanied by an IAEA-NDS-report which should give the data user all necessary documentation on contents, format and origin of the data library.

IAEA-NDS-reports are updated whenever there is additional information of relevance to the users of the data library.

For citations care should be taken that credit is given to the author of the data library and/or to the data center which issued the data library. The editor of the IAEA-NDS-report is usually not the author of the data library.

Neither the originator of the data libraries nor the IAEA assume any liability for their correctness or for any damages resulting from their use.

 

 

96/11

Citation guideline:

This data library should be cited as follows:

"FENDL/E-2.0, Evaluated nuclear data library of neutron nuclear interaction cross sections and photon production cross sections and photon-atom interaction cross sections for fusion applications, released on May 15, 1998", summary documentation A.B. Pashchenko, and H. Wienke, report IAEA-NDS-175 Rev. 1 (International Atomic Energy Agency, March 1997). Data library FENDL/E version May 15, 1998, received on tape (or retrieved online) from the IAEA Nuclear Data Section.

 

 

 

 

Table of Contents

Summary

References

Appendix A: List of FENDL/E-2.0 evaluations for neutron interaction and photon production cross sections

Appendix B: List of FENDL/E-2.0 evaluations for photon-atom interactions taken from ENDF/B-VI photon-atom interaction library

Attachment: Distribution of FENDL-2 Library

 

 

 

 

FENDL/E-2.0

Evaluated nuclear data library of neutron nuclear interaction cross sections, photon production cross sections and photon-atom interaction cross sections for fusion applications

Released on May 15, 1998

Summary documentation by
A.B. Pashchenko and H. Wienke

 

 

Summary

The library FENDL/E-2.0, version 1 of March 1997, contains selected evaluated neutron, photon-atom, and photon production cross sections, in ENDF format, with resonance parameters where appropriate, for 57 nuclides of importance for coupled neutron-photon transport calculations for fusion reactor design. The energy ranges from 10-5 eV up to 20 MeV. The library has been developed from the previous version FENDL/E-1.1 [ Ref. 1] by including thirteen replacing evaluations and six for additional materials. The new evaluations were selected by the FENDL/E-2.0 selection committee [Refs. 2,3], according to the procedure agreed upon at the IAEA Advisory Group Meeting on "Completion of FENDL-1 and Start of FENDL-2", Del Mar, California, USA, 5-9 Dec. 1995 [Ref. 4], from candidate evaluations submitted by five national projects viz. JENDL-FF (Japan), BROND (Russia), EFF (European Union), ENDF/B-VI (USA) and CENDL (China).

The neutron-nucleus interaction and photon production cross sections have been selected from the following evaluated nuclear data libraries:

- BROND-2: BROND library version 2 contributed by the Russian Federation, see document IAEA-NDS-90 Rev. 8. [Ref. 5]

- ENDF/B-VI.x: ENDF/B library version VI, revision x contributed by the U.S.A., see document IAEA-NDS-100 Rev. 6. [Ref. 6]. Note that revision x is the revision number of the given material, not of the library.

- JENDL-3.1: JENDL library version 3.1 contributed by Japan, see document IAEA-NDS-110 Rev. 4. [Ref. 7].

- JENDL-FF: JENDL Fusion file contributed by Japan [Ref. 8].

- EFF-3: European Fusion library version 3 contributed by the European Community [Ref. 9].

BROND-2, ENDF/B-VI, JENDL-FF and EFF-3 are in ENDF-6 format, see document IAEA-NDS-76 Rev. 4. [Ref. 10], JENDL-3.1 is in ENDF-5 format, see document IAEA-NDS-75, Rev.1 [Ref. 11]. The FENDL/E-1.0 Evaluations for photon-atom interaction are all taken from ENDF/B-VI photon-atom interaction Library, see report IAEA-NDS-58 Rev.2 [ Ref. 12].

The preliminary selection of evaluations for inclusion in FENDL/E-2.0 was made at the IAEA Consultant's Meeting on "Selection of Basic Evaluations for the FENDL-2 Library", held at Karlsruhe, Germany, June 24-28, 1996 [Ref. 3]. This preliminary selection was established by applying the following criteria [Refs. 3,4,13]:

- Presence of gamma ray production cross sections and spectra

- Correlated energy-angle neutron and charged particle emission data (MF=6).

- Recoil distributions in MF=6 format for major structural materials (recommended for other materials).

- Energy balance better than 2% at all energies.

- MF=1 descriptive information.

- Presence of uncertainty information.

- Use of Standard Reference Data such as IRDF-90.2 dosimetry cross sections in candidate files highly recommended.

For the final adoption of the pre-selected evaluations several actions, requested at the last mentioned meeting, were completed by the contributing parties. Based upon the results of these actions the final adoption was made at the IAEA Advisory Group Meeting on "Extension and Improvement of the FENDL Library for Fusion Applications (FENDL-2)", held in Vienna, March 3-7, 1997 [Ref. 14 ]. At this meeting it was agreed to include in the basic library FENDL/E-2.0 also the ENDF/B-6 evaluations for 3,4He and 197Au. These have not been reviewed for FENDL but are contained in the current processed libraries as their need was recognized since the materials are used in fusion applications. Also the JENDL-3 evaluation for natGa was included as this material is used as a coolant in fusion reactors. The selected evaluation does not satisfy the criteria setup for FENDL evaluations (no g-production data) but is the only available data file.

Table 1 lists the materials included in FENDL/E-2.0.

The data are available from the IAEA Nuclear Data Section in ftp subdirectory "UD7: [FENDL2.TRANSPORT.FENDLE]". This subdirectory has a total size of about 51.4 Megabytes and includes 57 data files plus a file named aaareadme.www containing the information presented in this summary. The nuclear data files for each of the isotopes/elements have been identified individually with names such as:

"H002BR2.DAT" for the data of H-2 from BROND-2,

"SI030E6.DAT" for the data of Si-30 from ENDF/B-VI,

"MO000JFF.DAT" for the data of Mo-nat from JENDL-FF,

"FE056EFF3.DAT" for the data of Fe-56 from EFF-3

"TA181J3.DAT" for the data of Ta-181 from JENDL-3.1

The atomic number is always written with three digits, starting with a '0' when it is smaller than 100 and '00' when smaller than 10.

All the photon-atom interaction cross section data are available in one single file named "FENDLEP.dat". A list of FENDL/E-2.0 evaluations for neutron interaction and photon production cross sections is presented in Appendix A and that of evaluations for photon-atom interactions in Appendix B.

 

 

 

 

Table 1: Materials included in FENDL/E-2.0

Neutron interaction cross sections for the isotopes:

ENDF/B-VI: 1H, 3H, 3He, 4He, 6Li, 7Li, 10B, 11B, 19F, 28-30Si, 31P, S, Cl, K, V,50,52-54Cr, 55Mn, 54,57,58Fe, 59Co, 58,60-62,64Ni, 63,65Cu, 197Au,206-208Pb
JENDL-3: 23Na, Mg, Ca, Ti, 55Mn, Ga, 181Ta, 209Bi
BROND-2: 2H,15N, Sn
JENDL-FF: 9Be, 12C, 14N, 16O, 51V, Zr, 93Nb, Mo, W
EFF-3: 27Al, 56Fe

Photon-atom interaction cross sections for the elements:

ENDF/B-VI: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Ga, Zr, Nb, Mo, Sn, Ba, Ta, W, Au, Pb, Bi.

As was agreed at the Del Mar-95 AGM the contributors of the new evaluations also provided to the NDS the processed cross section data which were derived from the these evaluations with the nuclear data processing code NJOY [Ref. 15]. The processed cross sections were in pointwise ACE format, for use with the Monte Carlo transport code MCNP [Ref. 16], and in the multigroup GENDF and MATXS formats, for use in coupled neutron-photon transport calculations with discrete-ordinates codes like ANISN, ONEDANT, etc, to be included in the working sublibraries FENDL/MC-2.0 and FENDL/MG-2.0 [Ref. 17] respectively.

These processed contributions, however, were primarily generated for the purpose of benchmark analysis and, as was found upon closer inspection at IAEA/NDS, the specifications for processing, used by the various contributing parties, were not uniform. Therefore and also in view of the improvements and new options incorporated in the most recent version of NJOY94, it was agreed, at the Vienna-97 Advisory Group Meeting, that all evaluations, including those carried over from FENDL/E-1.0, should be reprocessed, using NJOY94 version 61 and later versions. Each party should process their own selected evaluations and the processed multigroup and ACE data files should be submitted to IAEA/NDS by October 1, 1997. Quality assurance tests will be performed by J. White, RSIC, ORNL, USA, and results submitted to IAEA/NDS by November 30.

References

1. A.B. Pashchenko, H. Wienke, S. Ganesan and P.K. McLaughlin, "FENDL/E, Evaluated Nuclear Data Library of Neutron Interaction Cross Sections, Photon Production Cross Sections and Photon-Atom Interaction Cross Sections for Fusion Applications, version 1.1 of November 1994", IAEA(NDS)-128, Rev. 3 (February 1996)

2. IAEA Consultants' Meeting on "Selection of Basic Evaluations for the FENDL-2 Library", Karlsruhe, Germany, June 1996; summary report prepared by A.B. Pashchenko and published as report INDC(NDS)-356, September 1996

3. IAEA Advisory Group Meeting on "Extension and Improvement of the FENDL Library for Fusion Applications (FENDL-2)", summary report to be published

4. IAEA Advisory Group Meeting on "Completion of FENDL-1 and Start of FENDL-2", Del Mar, California, USA, 5-9 December 1995, summary report prepared by A.B. Pashchenko and published as report INDC(NDS)-352, March 1996

5. V.N. Manokhin et al.,"BROND-2.2 Russian Evaluated Neutron Reaction Data Library Summary documentation, H.D. Lemmel and P.K. McLaughlin, IAEA-NDS-90 Rev. 8 (January 1994)

6. P.F. Rose (Editor), "ENDF-6 Summary Documentation", 4th Edition of BNL-NCS-17541 (=ENDF-201) (October 1991), U.S. National Nuclear Data Center, Brookhaven National Laboratory, Upton, N.Y., USA. The IAEA documentation is presented in "ENDF-6 The U.S. Evaluated Nuclear data Library for Neutron Reaction Data by the U.S. National Nuclear Data Center including revisions up to June 1993", IAEA-NDS-100, Rev. 6 (June 1995)

7. K. Shibata et al., "Japanese Evaluated Nuclear Data Library, Version 3, JENDL-3, JAERI-1319 (1990), IAEA Nuclear Data Services documentation, IAEA-NDS-110, Rev. 4. (June 1992)

8. S. Chiba et al.: "Evaluation of JENDL Fusion File", JAERI-M 92-027, pp. 35-44(1992).

9. J. Kopecky, H. Gruppelaar, A. Hogenbirk, H.A.J. van der Kamp, D. Nierop, "European Fusion File EFF-2.4", report ECN-C-94-16 (Netherlands Energy Research Foundation, ECN, 1994). Data library EFF-2.4, maintained by the Netherlands Energy Research Foundation for the Fusion Programme of the European Community, received from the OECD NEA Data Bank in January 1995.

10. P.F. Rose and C.L. Dunford, ENDF-102, "Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6", U.S. National Nuclear Data Center, Brookhaven National Laboratory, Upton, N.Y., USA, BNL-NCS-44945(October 1991). The IAEA documentation is presented in "ENDF-6 Formats Manual", IAEA-NDS-76, Rev .4 (January 1992)

11. R. Kinsey and B.A. Magurno, "ENDF-5 Formats Manual", (1984), IAEA Nuclear Data Services documentation, IAEA-NDS-75, Rev. 1 (September 1986)

12. "EN6-PHOTO and JEF-2/PHOTO Photo-atomic Interaction Data Library" by the Lawrence Livermore National Laboratory, USA. Summary documentation by H.D. Lemmel, report IAEA-NDS-58, Rev. 4, (International Atomic Energy Agency, Sept. 1994)

13. S. Ganesan (Compiler), "Improved Evaluations and Integral Data Testing for FENDL", Summary report of an IAEA Advisory Group Meeting held at Garching near Munich, Germany, September 1994, report INDC(NDS)-312 (December 1994)

S. Ganesan (Compiler), "Review of Uncertainty Files and Improved Multigroup Cross Section Files for FENDL", summary report of an IAEA Advisory Group Meeting held in cooperation with the Japan Atomic Energy Research Institute, Tokai Research Establishment, JAERI, Japan, 8-12 November 1993, report INDC(NDS)-297 (January 1994)

14. IAEA AGM on "Extension and Improvement of the FENDL Library for Fusion Applications", IAEA headquarters, Vienna, 3-7 March 1997, summary report by A. B. Pashchenko and M. Herman and published as INDC(NDS)-372, 1997

15. R.E. MacFarlane and D. M. Muir, "The NJOY Nuclear Data Processing System, Version 91", Los Alamos National Laboratory report LA-12740-M (1994)

16. Judith F. Briesmeister, Ed, "MCNP-A General Monte Carlo N-Particle Transport Code,Version 4A", Los Alamos National Laboratory report LA-12625-M (1993)

17. "FENDL/MG-2.0 and FENDL/MC-2.0, The processed cross-section libraries for neutron-photon transport calculations, version 1". Summary documentation M. Herman and H. Wienke, report IAEA-NDS-176 Rev. 0, to be published

 

Appendix A

List of FENDL/E-2.0 Evaluations for neutron interaction

and photon production

MATERIAL LIBRARY

MAT Number

File name in online system

Number of records

H-1 ENDF/B-VI.1 125 H001E6.DAT 2117
H-2 BROND-2.1 102 H002BR.DAT 496
H-3 ENDF/B-VI.0 131 H003E6.DAT 732
He-3 ENDF/B-VI.1 225 HE003E6.DAT 455
He-4 ENDF/B-VI.0 228 HE004E6.DAT 373
Li-6 ENDF/B-VI.1 325 LI006E6.DAT 2621
Li-7 ENDF/B-VI.0 328 LI007E6.DAT 4945
Be-9 JENDL-FF 425 BE009JFF.DAT 17230
B-10 ENDF/B-VI.1 525 B010E6.DAT 4594
B-11 ENDF/B-VI.0 528 B011E6.DAT 8531
C-12 JENDL-FF 625 C012JFF.DAT 2613
N-14 JENDL-FF 725 N014JFF.DAT 8780
N-15 BROND-2.1 720 N015BR.DAT 4917
O-16 JENDL-FF 825 O016JEF.DAT 6222
F-19 ENDF/B-VI.0 925 F019E6.DAT 9485
Na-23 JENDL-3.1 3111 NA023J3.DAT 4711
Mg-nat JENDL-3.1 3120 MG000J3.DAT 4254
Al-27 EFF-3.0 3131 AL027EFF3.DAT 13183
Si-28 ENDF/B-VI.5 1425 SI028E6.DAT 10241
Si-29 ENDF/B-VI.5 1428 SI029E6.DAT 9685
Si-30 ENDF/B-VI.5 1431 SI030E6.DAT 6777
P-31 ENDF/B-VI.0 1525 P031E6.DAT 848
S-nat ENDF/B-VI.0 1600 S000E6.DAT 4594
Cl-nat ENDF/B-VI.0 1700 CL000E6.DAT 4269
K-nat ENDF/B-VI.0 1900 K000E6.DAT 3727
Ca-nat JENDL-3.1 3200 CA000J3.DAT 5260
Ti-nat JENDL-3.1 3220 TI000J3.DAT 5243
V-51 JENDL-FF 2328 V051JFF.DAT 9194
Cr-50 ENDF/B-VI.1 2425 CR050E6.DAT 6807
Cr-52 ENDF/B-VI.1 2431 CR052E6.DAT 8492
Cr-53 ENDF/B-VI.1 2434 CR053E6.DAT 8520
Cr-54 ENDF/B-VI.1 2437 CR054E6.DAT 5513
Mn-55 ENDF/B-VI.0 2525 MN055E6.DAT 17970
Fe-54 ENDF/B-VI.1 2625 FE054E6.DAT 7992
Fe-56 EFF-3.0 2631 FE056EFF3.DAT 62212
Fe-57 ENDF/B-VI.1 2634 FE057E6.DAT 11156
Fe-58 ENDF/B-VI.1 2637 FE058E6.DAT 7404
Co-59 END/BVI.1 2725 CO059E6.DAT 7878
Ni-58 ENDF/BVI.1 2825 NI058E6.DAT 9956
Ni-60 ENDF/BVI.1 2831 NI060E6.DAT 6716
Ni-61 ENDF/BVI.1 2834 NI061E6.DAT 6984
Ni-62 ENDF/BVI.1 2837 NI062E6.DAT 5739
Ni-64 ENDF/BVI.1 2843 NI064E6.DAT 5100
Cu-63 ENDF/BVI.2 2925 CU063E6.DAT 9460
Cu-65 ENDF/BVI.2 2931 CU065E6.DAT 7943
Ga-nat JENDL-3.2 3100 GA000J3.DAT 8456
Zr-nat JENDL-FF 4000 ZR000JFF.DAT 13145
Nb-93 JENDL-FF 4193 NB093JFF.DAT 6864
Mo-nat JENDL-FF 4200 MO000JFF.DAT 18228
Sn-nat BROND-2.1 5000 SN000BR.DAT 3633
Ta-181 JENDL-3.1 3731 TA181J3.DAT 4617
W-nat JENDL-FF 7400 W000JFF.DAT 14345
Au-197 ENDF/B-VI.1 7925 AU197E6.DAT 1030
Pb-206 ENDF/B-VI.0 8231 PB206E6.DAT 8050
Pb-207 ENDF/B-VI.1 8234 PB207E6.DAT 8046
Pb-208 ENDF/B-VI.0 8237 PB208E6.DAT 5520
Bi-209 JENDL-3.1 3831 BI209J3.DAT 4227

Appendix B

List of FENDL/E-2.0 Evaluations for photon-atom interaction taken from ENDF/B-VI photon-atom interaction library

MATERIAL

MAT No.

No.Records

AL000 1300 1610
B000 500 1277
BA000 5600 2311
BE000 400 883
BI000 8300 2836
C000 600 1198
CA000 2000 1629
CL000 1700 1599
CO000 2700 1904
CR000 2400 1838
CU000 2900 1737
F000 900 1263
FE000 2600 1845
H000 100 833
K000 1900 1635
LI000 300 911
MG000 1200 1309
MN000 2500 1882
MO000 4200 2118
N000 700 1292
NA000 1100 1368
NB000 4100 2184
NI000 2800 1870
O000 800 1207
P000 1500 1576
PB000 8200 2840
S000 1600 1573
SI000 1400 1607
SN000 5000 2327
TA000 7300 2652
TI000 2200 1882
V000 2300 1882
W000 7400 2668
ZR000 4000 2190

Attachment

DISTRIBUTION OF THE FENDL-2 LIBRARY

(As recommended at the IAEA Advisory Group Meeting on FENDL,

held at IAEA Headquarters, Vienna, Austria, March 1997.)

The master copy of the FENDL-2 library resides with the Nuclear Data Section of the International Atomic Energy Agency. To facilitate user access to the library the official copy of FENDL-2 will be distributed to the major nuclear data centres in Europe (NEA Data Bank, Paris), Japan (JNDC, Tokai-mura), Russia (CJD,Obninsk) and USA (NNDC, Brookhaven and RSIC, Oak Ridge). As agreed between data centers, sharing common FENDL information, the recipients are receiving now the same products from all above centers. The data are available and may be further distributed to the user community according to the customer service options given below. Each FENDL sub-library will be in a single data set, i.e. Activation, Decay, etc. in the 8 mm tape, 6 mm tape, 4 mm tape or standard 9 track magnetic tape (6250 bpi or 1600 bpi) and CD-ROM options. The interested scientists may request FENDL-2 (or parts of it) directly from the IAEA/NDS or from one of these centers.

FENDL CUSTOMER SERVICE OPTIONS

MEDIA FORMAT By WHOM
Electronic FTP IAEA, NEADB, NNDC
4 mm tape UNIX TAR
VAX BACKUP

ASCII
CJD, IAEA, NEADB, NNDC, RSIC
CJD, IAEA, NEADB, NNDC

NEADB
6 mm tape UNIX TAR
VAX BACKUP

ASCII
NEADB
NEADB

NEADB
8 mm tape UNIX TAR
VAX BACKUP

ASCII
NEADB, NNDC, RSIC
NEADB, NNDC

NEADB
9 track ASCII
EBCDIC
CJD, IAEA
CJD, IAEA
CDROM UNIX TAR
ASCII
RSIC
NEADB

Table notes

1) NNDC will distribute FENDL unprocessed data
2) RSIC will distribute FENDL processed data
3) RSIC offers cost free service to ITER customers