The aim of this study is to investigate the available U233 cross section data for adequate calculation of critical benchmark experiments, to calculate the multiplication factor Keff for several benchmarks in both fast and thermal energy ranges. The evaluation of the U233 has been investigated using SAMMY code, in order to generate a useful database for criticality calculations; the computer code FITWR for experimental data fitting shows the same results obtained from the Bayes method included within the SAMMY code, with a slight difference in the results in the evaluated cross sections due to different mathematical methods having different results. Excellent results for the calculated Keff values are obtained for several benchmarks in the thermal and fast benchmarks considered in this study.

Issue Section:
Technical Brief
Keywords:
ENDF, JENDL, benchmark
Topics:
Bayes methods, Computers, Cross section (Physics), Databases, Fittings, Thermal energy, Nuclear fission, Computer software, Neutrons

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