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

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

Oak Ridge National Laboratory

关键词: Reactor Kinetics;    99 General And Miscellaneous//Mathematics, Computing, And Information Science;    Multiplication Factors;    S Codes;    Mixed Oxide Fuels;   

DOI  :  10.2172/752979
RP-ID  :  ORNL/TM-1999/299
RP-ID  :  AC05-00OR22725
RP-ID  :  752979

美国|英语

来源: UNT Digital 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.