Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations, 1; Overview of comparison of nuclear data processing

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

Comparison of the nuclear data processing code is realised using nuclear data processing code FRENDY which has been developed in JAEA. In this study, we compared the difference of the nuclear data processing codes between FRENDY and NJOY. The impact of difference between open nuclear data processing codes on neutron transport calculations were also investigated. In this presentation, the difference of the nuclear data processing method between FRENDY and NJOY and ACE verification project carried out by IAEA.

Language	:	Japanese
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Meeting title	:	日本原子力学会2020年春の年会
Held date	:	2020/03
Location (city)	:	福島
Location (country)	:	日本
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DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	FRENDY; NJOY; 核データ処理; 独立検証; ACEライブラリ; シミュレーション信頼性
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Registration No. : BB20191716
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