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.)

11:30 AM - 11:45 AM

[3I05] Development of Nuclear Uncertainty Reduction Methodology for Spent Fuel Pit using Critical Experimental Data

(3)Uncertainty Evaluation for Sub-Criticality of Spent Fuel Pit

*Takanori Kitada1, Satoshi Takeda1, Hiroki Koike2, Daisuke Sato2, Toshikazu Takeda3 (1. Osaka University, 2. MHI, 3. Fukui University)

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

使用済燃料ピットの未臨界性評価を対象とし、核的不確かさを評価した結果を紹介する。断面積調整法、バイアス因子法等を用いて不確かさを評価し、不確かさ低減効果を核種・反応ごとの内訳とともに明らかにした。