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

•The uncertainty of pressure load caused by ex-vessel steam explosion is assessed by probability analysis.•The probability distributions of pressure peak and pressure impulse are obtained.•The initial parameters that have great influence on steam explosion are clarified. In nuclear reactor severe ac...

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Veröffentlicht in:Annals of nuclear energy 2022-10, Vol.176, p.109260, Article 109260
Hauptverfasser: Wu, Liangpeng, Sun, Ruiyu, Chen, Ronghua, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
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Sprache:eng
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Zusammenfassung:•The uncertainty of pressure load caused by ex-vessel steam explosion is assessed by probability analysis.•The probability distributions of pressure peak and pressure impulse are obtained.•The initial parameters that have great influence on steam explosion are clarified. 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.
ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2022.109260