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.)

11:15 AM - 11:30 AM

[3I04] Development of Nuclear Uncertainty Reduction Methodology for Spent Fuel Pit using Critical Experimental Data

(2)Uncertainty Evaluation by Cross Section Adjustment and Applicable Covariance Data

*Toshikazu Takeda1, Satoshi Takeda2, Takanori Kitada2, Hiroki Koike3, Daisuke Sato3 (1. University of Fukui, 2. Osaka University, 3. Mitsubishi Heavy Industries)

Keywords:Spent Fuel Pit, Critical Experiment, Nuclear Uncertainty, Covariance Data, Cross-section Adjustment Method

使用済燃料ピットの未臨界性評価における核的不確かさを、断面積調整法を用いて作成された共分散データに基づいて推定する方式について述べる。また、不確かさ評価に用いるべき断面積共分散データについて提案し、従前の共分散データとの違いについて述べる。