Neutronics benchmarks of mixed-oxide fuels using the SCALE/CENTRM sequence.

Hollenbach, D. F. ; Fox, P. B.

Technical Information Center Oak Ridge Tennessee

关键词: Mixed Oxide Fuels;    Reactor Kinetics;    S Codes;    C Codes;    Neutron Flux;   

RP-ID  :  DE00752979

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

The purpose of this study is to determine and document the reactor physics parameters (multiplication factors, spatially dependent flux ratios, and spacially dependent reaction rates ) for several distinct sets of problems using two distinct resonance cross-section processing techniques. In SCALE, by default, resonances are processed using NITAWL, which utilizes the Nordheim Integral Treatment. The results produced using this sequence are considered to be the base results. A second set of results are produced by replacing NITAWL with CENTRM/PMC. CENTRM produces point-wise fluxes for a given geometry configuration and set of isotopes. Using these fluxes, PMC produces problem- dependent self-shielding cross sections. Both sequences use ENDF/B-V cross- section data.