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Target accuracy of MA nuclear data and progress in validation by post irradiation experiments with the fast reactor "JOYO"

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大木 繁夫; 横山 賢治; 沼田 一幸*; 神 智之*

Oki, Shigeo; Yokoyama, Kenji; Numata, Kazuyuki*; Jin, Tomoyuki*

マイナーアクチナイド(MA)核種のリサイクルを行う実用化高速炉サイクルシステムの開発のため、核燃料サイクル開発機構は、高速実験炉「常陽」を用いた燃料及びMAサンプルの照射後試験(PIE)解析に着手した。本論文は、MA核データの目標精度とPIE解析によるそれらの検証状況について述べる。最初に分析の行われたMAサンプルの解析結果より、ENDF/B-VI及びJENDL-3.3における241Am捕獲反応の核異性体比について再評価の必要性が示唆された。

To develop a commercialized fast reactor cycle system involving the recycling of minor actinide (MA) nuclides, Japan Nuclear Cycle Development Institute has launched the isotopic composition analysis of post irradiation examination (PIE) results for fuels and MA samples irradiated at the experimental fast reactor "JOYO". This paper presents the target accuracy of MA nuclear data, as well as the progress in validation of those by PIE analyses. The analysis result on the first examined MA sample suggested the necessity of re-evaluation of the isomeric ratio for 241Am capture reaction both in ENDF/B-VI and in JENDL-3.3.

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