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Analysis of Thermal Benchmarks Based on the Evaluated Nuclear Data Files JEF-2 and ENDF/B-VI

Authors :
W. Bernnat
J. Keinert
M. Mattes
R. Seidel
Source :
Nuclear Data for Science and Technology ISBN: 9783642634734
Publication Year :
1992
Publisher :
Springer Berlin Heidelberg, 1992.

Abstract

For the validation of the recently released evaluated nuclear data files JEF-2 and ENDF/B-VI a first set of benchmark calculations for thermal systems important for criticality safety and LWR-neutronics were performed and compared with corresponding calculations based on JEF-1 and the MCNP-3B library (ENDF/B-IV, ENDL-85). The processing of the JEF-2 and ENDF/B-VI data which are given in the ENDF-6 format was performed by an updated version of the nuclear data processing system NJOY. Both multigroup libraries with 316 groups in MATXS-format and MCNP-libraries (continuous data with a very fine energy resolution) based on JEF-2 and ENDF /B-VI were generated. The ORNL uranyl nitrate benchmarks as well as the PNL Pu nitrate benchmarks were analysed by deterministic (ANISN/ONEDANT-S N -method) and Monte Carlo methods (MCNP-3B). The group constants for the S N -calculations were generated by a combination of TRAMIX and RSYST/CGM.

Details

ISBN :
978-3-642-63473-4
ISBNs :
9783642634734
Database :
OpenAIRE
Journal :
Nuclear Data for Science and Technology ISBN: 9783642634734
Accession number :
edsair.doi...........fcefb7610c538ac32a6e4fd02ddf5adf