Open AccessNeutronics benchmarks of mixed-oxide fuels using the SCALE/CENTRM sequence
Author(s) -
D.F. Hollenbach,
P B Fox
Publication year - 2000
Language(s) - English
Resource type - Reports
DOI - 10.2172/752979
Subject(s) - neutron transport , sequence (biology) , scale (ratio) , cross section (physics) , electromagnetic shielding , nuclear physics , flux (metallurgy) , set (abstract data type) , neutron flux , physics , nuclear engineering , neutron , computer science , materials science , chemistry , engineering , biochemistry , quantum mechanics , programming language , metallurgy
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