Journal
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
Volume 53, Issue 3, Pages 406-424Publisher
TAYLOR & FRANCIS LTD
DOI: 10.1080/00223131.2015.1054911
Keywords
FCA-IX assemblies; uranium; criticality; benchmark; Monte Carlo; deterministic method; JENDL-4.0; ENDF/B-VII.1
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New benchmark models with respect to criticality data are established on the basis of seven uranium-fueled assemblies constructed in the ninth experimental series at the fast critical assembly (FCA) facility. By virtue of these FCA-IX assemblies, where the simple combinations of uranium fuel and diluent (graphite and stainless steel) in their core regions were systematically varied, the neutron spectra of these benchmark models cover those of various reactor types, from fast to sub-moderated reactors. The sample calculations of the benchmark models by a continuous-energy Monte Carlo (MC) code showed obvious differences between even the latest versions of two major nuclear data libraries, JENDL-4.0 and ENDF/B-VII.1. The present benchmark models would be well suited for the assessment and improvement of the nuclear data for U-235, U-238, graphite, and stainless steel. In addition, the verification of the deterministic method was performed on the benchmark models by comparison with the MC calculations. The present benchmark models are also available to users of deterministic calculation codes for the assessment and improvement of nuclear data.
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