2020 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[3I01-05] Uncertainty Evaluation

Wed. Mar 18, 2020 10:30 AM - 11:55 AM Room I (Lecture Bildg. M 2F M-23)

Chair:Tomohiro Endo(Nagoya Univ.)

11:00 AM - 11:15 AM

[3I03] Development of Nuclear Uncertainty Reduction Methodology for Spent Fuel Pit using Critical Experimental Data

(1)Objective and Outline of Methodology

*Hiroki Koike1, Daisuke Sato1, Toshikazu Takeda2, Satoshi Takeda3, Takanori Kitada3 (1. MHI, 2. Univ. of Fukui, 3. Osaka Univ.)

Keywords:Spent fuel pit, Sub-criticality evaluation, Nuclear uncertainty, Critical experiment, Sensitivity coefficient, Covariance, Data assimilation method, Cross-section adjustment method, Bias factor method

使用済燃料ピット(SFP)の未臨界性評価において考慮すべき不確かさを定量化し、低減する手法を開発した。多数の臨界実験解析により得られるバイアス因子を用いて設計体系のバイアス因子を推定する新たなバイアス因子法(回帰バイアス因子法)を考案し、不確かさ低減への活用方法を示した。