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Konno, Chikara
JAEA-Conf 2026-001, p.115 - 120, 2026/06
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 of JENDL-5 with the AMPX-6 code bundled in SCALE6.2. In this nuclear data processing I found out that several produced AMPX continuous energy files of the thermal scattering law data in JENDL-5 had strange cross section data. I examined reasons why the strange cross section data were produced in detail and specified that an inadequate processing method of the thermal scattering law data in AMPX-6 caused the strange cross section data. I improved AMPX-6 and obtained adequate AMPX continuous energy files of the JENDL-5 thermal scattering law data.
Konno, Chikara
JAEA-Conf 2026-001, p.28 - 33, 2026/06
Activation analyses are essential in planning and execution of reactor decommissioning, where the ORIGEN-2 and ORIGEN-S codes are often used in Japan. This presentation points out problems in these codes and introduces the ORIGEN code, which is bundled in the US nuclear safety analysis code system SCALE6.2 or later. ORIGEN solves most of the problems but SCALE6.2 bundles only the libraries from the nuclear data library ENDF/B-VII.0 or later. Thus I produced new libraries for the ORIGEN code from JENDL-5. I also present remarks on calculations with the two-dimensional Sn code DORT which is often used to calculate neutron spectra for activation analyses.
Konno, Chikara
JAEA-Data/Code 2025-019, 70 Pages, 2026/03
JAEA-Data-Code-2025-019.pdf:4.47MB
AMPX format libraries were produced from the evaluated nuclear data library JENDL-5 to make JENDL-5 usable in the US nuclear safety analysis code systems SCALE6.2 and SCALE6.3, which are widely used in Japan. The produced libraries are an AMPX continuous energy library, AMPX multigroup libraries and AMPX covariance libraries. This report explains in detail how to produce the libraries and describes test calculation results for verification of the AMPX libraries.
Pyeon, C. H.*; Yamanaka, Masao*; Fukushima, Masahiro
Nuclear Science and Engineering, 195(8), p.877 - 889, 2021/08
Times Cited Count：6 Percentile：45.56(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.
