Probability analysis of ex-vessel steam explosion induced pressure load based on analysis code SEINA

被引:3
作者
Wu, Liangpeng [1 ,2 ,3 ]
Sun, Ruiyu [1 ,2 ,3 ]
Chen, Ronghua [1 ,2 ,3 ]
Tian, Wenxi [1 ,2 ,3 ]
Qiu, Suizheng [1 ,2 ,3 ]
Su, G. H. [1 ,2 ,3 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Shaanxi, Peoples R China
[2] Xi An Jiao Tong Univ, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian, Peoples R China
[3] Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian, Peoples R China
基金
国家重点研发计划;
关键词
FCI; Steam explosion; Probability analysis; Numerical simulation; RETENTION;
D O I
10.1016/j.anucene.2022.109260
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In nuclear reactor severe accidents, the interaction of molten core melt and coolant may lead to steam explosion, which seriously threatens the safety of the reactor. The four initial parameters that affect the steam explosion were randomly sampled and calculated multiple times by steam explosion analysis code SEINA, and the probability distributions of steam explosion pressure peak and pressure impulse under uncertain initial conditions are obtained. The results show that the peak pressure of ex-vessel steam explosion is roughly normally distributed, and the pressure peak of 90% of the cases under submerged and non-submerged conditions within the range of 10-60 MPa and 20-80Mpa. respectively. By calculating the four key correlation coefficients between input parameters and output parameters, it is concluded that the influence of melt temperature and breach size on output parameters is greater than that of system pressure and coolant temperature. (C) 2022 Elsevier Ltd. All rights reserved.
引用
收藏
页数:11
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