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JENDL-4.0 Integral Testing for Fission Systems
R. D. McKnight,Kazuteru Sugino,Go Chiba,Yasunobu Nagaya,Kenji Yokoyama,Teruhiko Kugo,Makoto Ishikawa,Shigeaki Okajima 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Benchmark testing for the newly developed Japanese evaluated nuclear data library JENDL-4.0 is carried out by using a huge amount of the integral data. Benchmark calculations are performed with the continuous-energy Monte Carlo code with a large number of neutron histories or with the deterministic procedure which has been developed for fast reactor analyses in Japan. In the present paper, representative benchmark results are shown as a rapid report. They are the results for criticality of low enriched UO_2 or MOX fueled light water moderated systems, of uranium or plutonium fuelled solution systems, of various fast reactors, and results of PIE analyses for a PWR spent fuel and actinoide samples irradiated in fast reactors.