Data Testing for ENDF/B-VII.1beta2

MacFarlane, Robert¹ 

[1] Los Alamos National Laboratory

关键词: Atomic and Nuclear Physics;    Nuclear Physics & Radiation Physics (73);    BENCHMARKS;    CRITICALITY;    CROSS SECTIONS;    EVALUATION;    MANUALS;    PROCESSING;    SAFETY;    TESTING;    ZERO POWER REACTORS;   

DOI  :  10.2172/1011061
RP-ID  :  LA-UR-11-10211
PID  :  OSTI ID: 1011061
Others  :  TRN: US1102156

美国|英语

来源: SciTech Connect

【 摘 要 】

Calculations have been performed for 390 critical assemblies from the International Handbook of Evaluated Criticality Safety Benchmark Experiments using the beta2 release of ENDF/B-VII.1. The results are compared to previous results for ENDF/B-VII. Cases that changed between the two versions are highlighted, and the results are discussed. The Cross Section Evaluation Working Group (CSEWG) is working on a new release of the ENDF/B-VII library of evaluated nuclear data, and the 'beta2' set of files was recently made available by the National Nuclear Data Center (NNDC). A set of about 850 input files for the MCNP Monte Carlo code to run critical assemblies from the International Handbook of Evaluated Criticality Safety Benchmark Experiments was available from our previous data testing work for ENDF/B-VII.0. We have now run 390 of those cases using data based on the beta2 files, and those results will be presented below. The ENDF files were downloaded from the NNDC to a Mac workstation. They were then processed using NJOY10 into ACE format files for use in the MCNP Monte Carlo code. The processing was limited to materials needed for the data testing work at this point. The existing MCNP input decks were used. No checking was done to see if any of the benchmarks had been updated since the ENDF/B-VII testing was finished. Most runs used 50 million histories in order to get Monte Carlo statistical uncertainties down the 0.01% range.