Identification of important parameters for source term analysis; Expectation of outcomes from fuel safety research

ソースターム解析ための支配因子の同定; 燃料安全性研究の成果への期待

Zheng, X. ; 杉山 智之 

Zheng, X.; Sugiyama, Tomoyuki

A suite of methodologies has been developed at JAEA for the source term uncertainty and sensitivity analyses during nuclear reactor severe accidents. Using the methodologies and integral severe accident codes, the uncertainty range of source term estimation can be quantified, and most influential factors can be identified. As shown in the results, some parameters from core component failure models have significant importance on the source term analysis. This study can lay groundwork for the improvement of numerical core component failure modeling in integral nuclear reactor severe accident simulation.