Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Fusion neutronics calculational benchmarks for basic nuclear data and transport codes intercomparison

Conference ·
OSTI ID:5794305
Four calculational benchmarks have been selected to compare various nuclear data libraries based on both ENDF/B-IV and V, and to compare results from various transport codes. Discrepancies up to 20% in tritium production from /sup 7/Li were found and have been attributed mainly to differences in current ENDF/B-IV and V evaluations, while approx.4% is attributed to differences in the group structure of the libraries used. Results from MCNP and VIP Monte Carlo codes are in good agreement, but MORSE calculations show good agreement only for high threshold reactions.
Research Organization:
California Univ., Los Angeles (USA). School of Engineering and Applied Science; Argonne National Lab., IL (USA); Wisconsin Univ., Madison (USA). Dept. of Nuclear Engineering
DOE Contract Number:
AS03-84ER52103
OSTI ID:
5794305
Report Number(s):
CONF-850507-61; ON: DE86009483
Country of Publication:
United States
Language:
English