Processing of FENDL-PA/1.1

Technical Report · Tue Feb 01 00:00:00 EST 1994

DOI:https://doi.org/10.2172/10141446· OSTI ID:10141446

Mann, F M; Lessor, D E; Carter, L L

The Fusion Evaluated Nuclear Data Library (FENDL) is an evaluated nuclear data library based upon the best evaluations from the world community. The library is maintained by the Nuclear Data Section of the International Atomic Energy Agency (IAEA). However, before the data can be used in computer codes, it must be processed into the appropriate format. The library containing the transmutation (or activation) cross sections that are part of FENDL is designated as FENDL-PA (P designating pointwise). The evaluations in Version 1.1 of this activation library were selected in the following two steps. For the most important reactions ({approximately}250), consultants to the IAEA compared evaluations submitted for consideration with experimental data. These evaluations included those from ENDF/B, JEF, BROND, JENDL, as well as ``complete`` activation libraries, such as EAF and REAC. The consultants then chose the ``best`` evaluation for each of the reactions. The evaluations for the remaining ({approximately}12,000) reactions were taken from EAF-3. The pointwise FENDL-PA/1.1 activation library was processed into two formats. Continuous energy format as used by the Monte Carlo neutron/photon transport code MCNP. ASCII 175 group multigroup format as used by the transmutation code REAC*2/3.

• Research Organization: Westinghouse Hanford Co., Richland, WA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 10141446
• Report Number(s): WHC-EP-0727; ON: DE94009761; BR: 35AF11201/35AF11202
• Resource Relation: Other Information: PBD: Feb 1994
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NUCLEAR REACTIONS
NUCLEAR DATA COLLECTIONS
INFORMATION RETRIEVAL
DATA PROCESSING
MONTE CARLO METHOD
EVALUATED DATA
CROSS SECTIONS
NEUTRON ACTIVATION ANALYSIS
NEUTRON TRANSPORT
TRANSMUTATION
663400
990301
SPECIFIC NUCLEAR REACTIONS AND SCATTERING
DATA HANDLING