Evaluation of Pressure History due to Steam Explosion

被引：0
作者：
Kim, Seung Hyun [1 ]
Chang, Yoon-Suk [1 ]
Song, Sungchu [2 ]
Hwang, Taesuk [2 ]
机构：
[1] Kyung Hee Univ, Dept Nucl Engn, Seoul, South Korea
[2] Korea Inst Nucl Safety, Daejeon, South Korea
来源：
TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS A | 2014年 / 38卷 / 04期
关键词：
External Reactor Vessel Cooling; In-vessel Retention; Severe Accident; Steam Explosion;
D O I：
10.3795/KSME-A.2014.38.4.355
中图分类号：
TH [机械、仪表工业];
学科分类号：
0802 ;
摘要：
Steam explosions can be caused by fuel-coolant interactions resulting from failure of the external vessel cooling system in a new nuclear power plant. This can threaten the integrity of structures, including the nuclear reactor and the containment building. In the present study, an improved technique for analyzing the steam explosion phenomenon was proposed on the basis of previous research and was verified by simulations involving alumina experiments. Also, the improved analysis technique was applied to determine the pressure history of the reactor cavity in accordance with postulated failure locations. The results of the analysis revealed that the effects of vessel side failure are more serious than those of vessel bottom failure, with approximately 70% higher maximum pressure.
引用
收藏
页码：355 / 361
页数：7
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