RSICC DATA PACKAGE DLC-222
1. NAME AND TITLE OF DATA LIBRARY
FENDL-2.1: Compendium of Reference and Processed Sub‑libraries Derived from International Evaluated Nuclear Data Files for Fusion Applications.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
No retrieval program is included in the package. Data are in ENDF‑6 and well known processed formats: GENDF (output of NJOY/GROUPR and NJOY/GAMINR), MATXS, and continuous energy format for use in MCNP calculations.
IAEA Nuclear Data Section, Vienna, Austria.
4. HISTORICAL BACKGROUND AND INFORMATION
The IAEA Nuclear Data Section (NDS), in cooperation with national nuclear reaction data centers and research groups, has established the international Fusion Evaluated Nuclear Data Library (FENDL). This library is a comprehensive collection of high-quality nuclear data, selected from the various existing national data libraries, covering the necessary nuclear input for physics and engineering studies of the nuclear performance of the International Thermonuclear Experimental Reactor (ITER) project and other fusion‑related development projects. Within the framework of the FENDL project, the IAEA/NDS played the critical organizational role in planning and coordinating the assembly, cross section processing and benchmark data testing of the FENDL library following the recommendations of a series of international meetings.
The FENDL project started in 1987 and the first version of the library, FENDL‑1, was officially released early in 1995. Extensive integral data testing of FENDL-1 led to an improved version designated as FENDL-2 which was finalized for general distribution in January 1999. FENDL-2 represents contributions from ENDF/B-VI (United States), JENDL-3 and JENDL-FF (Japan), BROND-2 (Russian Federation), and EFF-3 (European Union).
Participants at the IAEA Consultants' Meeting "Maintain FENDL Library for Fusion Applications", held in Vienna, 10-12 November, 2003, [INDC(NDS)-451] recommended unanimously an updating of the FENDL-2.0 transport libraries. The generation of the new library was undertaken by IAEA-NDS [INDC(NDS)-467] using NJOY-99.90, and the FENDL-2.1 data library is freely available from the IAEA-NDS upon request. It is also readily accessible at http://www-nds.iaea.org/fendl21/ web site.
The FENDL/DS-2.0 sublibrary for dosimetry was not updated; the use of IRDF-2002 is recommended instead. The FENDL/A-2.0 sublibrary for activation and FENDL/D-2.0 decay data sublibrary were not updated; use of EAF-2003 (JEFF-3.0/A) is recommended. No changes were recommended to the FENDL/C-2.0 charged-particle sublibrary, which is not included in this distribution but is available in the DLC-183/FENDL 2.0 package and on the IAEA NDS website.
5. APPLICATION OF THE DATA
The FENDL library is a comprehensive source of processed and benchmark tested nuclear data tailored to the requirements of the ITER EDA Project and other fusion‑related development projects.
6. SOURCE AND SCOPE OF DATA
FENDL-2.1 package includes the following information:
• FENDL/E-2.1 (ENDF format) data files for neutron and photo-atomic interaction data.
• FENDL/MC-2.1: (ACE format) continuous energy data files for MCNP calculations. All the files were created at 300K, and probability tables (PT) were generated for those materials with unresolved resonance data.
• FENDL/MG-2.1: (MATXS and GENDF format) FENDL/MG-2.1 contains neutron-photon coupled multi-group cross section data in MATXS and GENDF format. These data can be easily processed by the code TRANXS (PSR-317/TRANSX 2.15) for further use in deterministic transport codes such as DORT and TORT (which are distributed in CCC-650/DOORS 3.2a). The Vitamin-J energy structure was used for neutrons as well as photons to give 175 energy groups between 0.00001 eV and 19.64 MeV for neutrons, and 42 groups between 1 keV and 50 MeV for photons. Three files are supplied for each material: one with extension “.m” containing the MATXS-formatted cross section data, and two additional files with extensions “.g” and “.gam” containing the GROUPR and GAMINR output respectively in GENDF format (last two files are useful for sensitivity analysis).
• NJOY inputs for generation of FENDL-2.1.
• Auxiliary programs and MSDOS/WINDOWS batch procedures used in the generation and verification of the FENDL-2.1 transport libraries.
• ACEDOP (SIGACE package) allows Doppler broadening of resolved resonances in the ACE-formatted files except for the energy region described by unresolved resonance representation in the original ENDF-formatted files.
The use of isotopic evaluations for Cl, Ti, Mo and W increases the number of materials from 57 in FENDL-2.0 to 71 in FENDL-2.1.
H-1, H-2, H-3, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-12, N-14, N-15, O-16, F-19, Na-23, Mg-nat, Al-27, Si-28, Si-29, Si-30, P-31, S-nat, Cl-35, Cl-37, K-nat, Ca-nat, Ti-46, Ti-47, Ti-48, Ti-49, Ti-50, V-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Ga-nat, Zr-nat, Nb-93, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-100, Sn-nat, Ta-181, W-182, W-183, W-184, W-186, Au-197, Pb-206, Pb-207, Pb-208, Bi-209
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
No data retrieval program is included in the package. See note under item 2 above. The included SIGACE (ACEDOP) package comes with Windows executable and source codes. Executables have been run on operating systems up through Windows XP Version 2002 SP2.
8. DATA FORMAT AND COMPUTER
The ASCII data can be used on any computer platform and are distributed in individual ZIP files. RSICC ID: D00222MNYCP00.
9. TYPICAL RUNNING TIME
Run times vary.
a. Documentation available with library:
D. López Aldama and A. Trkov, “FENDL-2.1, Update of an evaluated nuclear data library for fusion applications,” Summary documentation. INDC(NDS)-467 (December 2004).
R. Forrest and A.Trkov, “Summary Report of an IAEA Consultants’ Meeting ‘Maintain FENDL Library for Fusion Applications’ FENDL-2 Library for Fusion Applications – Status and Future Developments,” INDC(NDS)-451 (November 2003).
b. Other useful documentation:
D.E. Cullen, "PREPRO 2004: 2004 ENDF/B Pre-processing Codes”, IAEA-NDS-39, Rev. 12 (Nov. 22, 2004).
"EN6‑PHOTO and JEF‑2/PHOTO Photo‑Atomic Interaction Data Library," (summary documentation by H. D. Lemmel) IAEA‑NDS‑58, Rev. 4 (September 1994).
R. E. MacFarlane, "The NJOY Nuclear Data Processing System, Version 91," LA‑12740‑M (1994).
11. CONTENTS OF LIBRARY
Included are the referenced documents in 10.a and the FENDL/E-2.1, FENDL/MC-2.1 and FENDL/MG-2.1 libraries and ACEDOP written in compressed ZIP files plus the NJOY input files. The entire package is about 235 MB when compressed.
12. DATE OF ABSTRACT
April 1999, revised August 2005.
KEYWORDS: MULTIGROUP CROSS SECTIONS; MATXS FORMAT; MCNP FORMAT