2019 Fall Meeting

Presentation information

Oral presentation

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

[1J16-20] Uncertainty Analysis

Wed. Sep 11, 2019 4:40 PM - 6:00 PM Room J (Common Education Bildg. 2F D22)

Chair:Tadafumi Sano(Kindai Univ.)

4:40 PM - 4:55 PM

[1J16] Uncertainty quantification of nuclides number densities after fuel depletion based on efficient random sampling method using sensitivity

*Go Chiba1 (1. Hokkaido University)

Keywords:Uncertainty quantification, Sensitivity, Control variate method

We have proposed an effiient random sampling method with sensitivity profiles and the control variate method. With this method, it becomes possible to estimate statistical quantities such as mean values and standard deviations with less number of samples than with the normal random sampling method. In this presentation, some numerical examples about uncertainty quantification of nuclide number densities after fuel depletion will be presented.