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 |
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
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
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.
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
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.
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
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 |
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