Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations, 4; Investigation of the impact of difference between nuclear data processes on nuclear calculations

Ono, Michitaka*; Tojo, Masayuki*; Tada, Kenichi ; Ikehara, Tadashi

JAEA develops a nuclear data processing code FRENDY. We can compare and verify the conventional nuclear data processing code using FRENDY. In this presentation, we explain the impact of the difference of the nuclear data processing codes on the neutronics calculations using MCNP.

Language	:	Japanese
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Meeting title	:	日本原子力学会2020年秋の大会
Held date	:	2020/09
Location (city)	:	福岡(online)
Location (country)	:	日本
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DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	FRENDY; 核データ処理; 独立検証; ACEライブラリ
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Registration No. : BB20200207
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