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※ 半角英数字
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Development of a unified cross-section set ADJ2010 based on adjustment technique for fast reactor core design

高速炉核設計用統合炉定数ADJ2010の開発

杉野 和輝; 石川 眞; 横山 賢治; 長家 康展; 千葉 豪; 羽様 平; 久語 輝彦; 沼田 一幸*; 岩井 武彦*; 神 智之*

Sugino, Kazuteru; Ishikawa, Makoto; Yokoyama, Kenji; Nagaya, Yasunobu; Chiba, Go; Hazama, Taira; Kugo, Teruhiko; Numata, Kazuyuki*; Iwai, Takehiko*; Jin, Tomoyuki*

高速炉核設計における核特性予測精度向上のために、国内では統合炉定数が開発されてきた。統合炉定数は広範囲に渡る積分実験情報を微分核データと結びつけるものであり、ベイズの定理に基づく断面積調整手法に基づいて作成される。現在、新しい炉定数ADJ2010が開発中である。本論文では、ADJ2010作成に向けてJENDL-4.0に基づく炉定数調整の結果を報告する。また、実用高速炉の核特性予測精度の評価にも言及する。ADJ2010は間もなく公開されるが、次世代高速炉の核設計に有効活用されることが期待される。

In order to improve the prediction accuracy of core performances in the fast reactor core design study, the unified cross-section set has been developed in Japan. The unified cross-section set, which combines a wide range of integral experimental information with differential nuclear data, is produced by using the cross-section adjustment technique based on the Bayesian parameter-estimation theory. A new set ADJ2010 is currently under development. The present paper describes the results of the cross-section adjustment for ADJ2010 which is based on the JENDL-4.0 data. The evaluation of the core design accuracy for a commercial power fast reactor core is also discussed. ADJ2010 will be released soon and will be expected to be utilized for core design of future fast reactors.

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