2018 Fall Meeting

Presentation information

Oral presentation

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

[1M01-04] Uncertainty Evaluation 1

Wed. Sep 5, 2018 10:00 AM - 11:10 AM Room M (E11 -E Building)

Chair:Tomohiro Endo(Nagoya Univ.)

10:45 AM - 11:00 AM

[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.