2018 Annual Meeting

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Oral presentation

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

[1F15-18] Uncertainty Evaluation 1

Mon. Mar 26, 2018 4:40 PM - 5:45 PM Room F (U2-211 -U2 Building)

Chair: Shunsuke Sato (CRIEPI)

5:25 PM - 5:40 PM

[1F18] Variance reduction on uncertainty analysis by random sampling method

(2)Variance reduction in burnup calculation

*Daiki Iwahashi1, Tomohiro Sakai1, Toshihisa Yamamoto1 (1. Nuclear Regulation Authority)

Keywords:MCCV method, MMC method, Burnup uncertainty analysis, Monte Carlo sampling

The Monte Carlo Control Variate (MCCV) method and the Multilevel Monte Carlo (MMC) method were applied to the combustion calculation of the fuel assembly. In addition, the effect of dispersion reduction on the uncertainty evaluation such as infinite multiplication factor and nuclide composition at the time of combustion is reported.