Cross-section-induced uncertainty evaluation of MA sample irradiation test calculations with consideration of dosimeter data

• 資料種別: 文書・図像類
• タイトル: Cross-section-induced uncertainty evaluation of MA sample irradiation test calculations with consideration of dosimeter data
• 著者・編者: Kazuteru, Sugino; Kazuyuki, Numata; Makoto, Ishikawa; Toshikazu, Takeda
• 著者標目: Kazuteru, Sugino; Kazuyuki, Numata; Makoto, Ishikawa; Toshikazu, Takeda
• 出版事項: ELSEVIER
• 出版年月日等: 2019-02-19
• 出版年（W3CDTF）: 2019-02-19
• タイトル（掲載誌）: Annals of Nuclear Energy
• 巻号年月日等（掲載誌）: 130
• 掲載巻: 130
• 掲載ページ: 118-123
• 本文の言語コード: eng
• 件名標目: Uncertainty; MA sample; Dosimeter; Neutron fluence scaling; Burnup sensitivity coefficient; JENDL-4.0
• 対象利用者: 一般
• 一般注記: In MA sample irradiation test data calculations, the neutron fluence during irradiation period is generally scaled by using dosimetry data in order to improve calculation accuracy. In such a case, appropriate correction is required to burnup sensitivity coefficients obtained by the conventional generalized perturbation theory because some cancellations occur in the burnup sensitivity coefficients. Therefore, a new formula for the burnup sensitivity coefficient has been derived with the consideration of the neutron fluence scaling (NFS) effect. In addition, the cross-section-induced uncertainty is evaluated by using the obtained burnup sensitivity coefficients and the covariance data based on the JENDL-4.0.
• オンライン閲覧公開範囲: 限定公開
• 関連情報（DOI）: 10.1016/j.anucene.2019.02.035
• 連携機関・データベース: 国立情報学研究所 : 学術機関リポジトリデータベース（IRDB）（機関リポジトリ）; https://irdb.nii.ac.jp
• 提供元機関・データベース: 福井大学 : 福井大学学術機関リポジトリ