Code Development of Total Sensitivity and Uncertainty Analysis for Reactor Physics Calculations

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Chenghui Wan
Liangzhi Cao
Hongchun Wu
Tiejun Zu
Wei Shen

Abstract

Sensitivity and uncertainty analysis are essential parts for reactor system to perform risk and policy analysis. In this study, total sensitivity and corresponding uncertainty analysis for responses of neutronics calculations have been accomplished and developed the S&U analysis code named UNICORN. The UNICORN code can consider the implicit effects of multigroup cross sections on the responses. The UNICORN code has been applied to typical pin-cell case in this paper, and can be proved correct by comparison the results with those of the TSUNAMI-1D code.

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