[1M01-04] Uncertainty Evaluation 1

[1M04] Investigation of uncertainty evaluation methodology for spent fuel pit due to nuclear data and manufacturing tolerances based on statistical approach

*Tetsuya Sugimura¹, Kazuki Kirimura¹, Hiroki Koike¹, Daisuke Sato¹, Toshikazu Takeda² (1. MHI, 2. Fukui Univ.)

Keywords:Spent fuel pit, Sub-criticality evaluation, Uncertainty, Nuclear data, Fabrication tolerance

In the sub-criticality evaluation for spent fuel pit, the effective neutron multiplication factor is conservatively evaluated. The evaluation is carried out by reflecting the uncertainty associated with analysis code including nuclear data-induced uncertainty, and the uncertainty associated with fabrication tolerance for fuel and structural materials. In the present study, an uncertainty evaluation methodology is developed based on the random sampling technique, in which the nuclear data uncertainty and the fabrication tolerances are simultaneously treated. As a result, the conservativeness is optimized. The outline of the methodology and the verification results are presented in this report.