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Pyeon, C. H.*; Yamanaka, Masao*; Fukushima, Masahiro
Nuclear Science and Engineering, 195(8), p.877 - 889, 2021/08
Times Cited Count：6 Percentile：51.52(Nuclear Science & Technology)Uncertainty quantification of lead (Pb) and bismuth (Bi) sample reactivity worth is numerically determined using the SCALE6.2 code system and experimental results obtained from the solid-moderated and solid-reflected core at the Kyoto University Critical Assembly (KUCA) to demonstrate the sensitivity coefficients of aluminum (Al) and Bi scattering reactions. From the results of the numerical analyses, the impact of 
Al and 
Bi scattering cross sections obtained using SCALE6.2/TSAR is disclosed on the Bi sample reactivity worth using Al reference and Bi test samples, although the uncertainty itself is small in the Bi sample reactivity worth.
Konno, Chikara
no journal, ,
The US nuclear safety analysis code system SCALE6.2 is also widely used in Japan, but the bundled AMPX continuous energy libraries are produced only from the US nuclear data library ENDF/B. Thus I produced an AMPX continuous energy library from the JENDL-5 neutron sub-library below 20 MeV. It was also confirmed that the produced library had no problem. The produced library will be released, which leads to dissemination of JENDL-5.
