An assessment methodology for in-vessel cerium retention by external reactor vessel cooling during severe accidents in PWRs

被引:11
|
作者
Park, JH
Jeong, YH
Baek, WP
Chang, SH
机构
[1] Korea Inst Nucl Safety, Regulatory Res Div, Taejon 305338, South Korea
[2] Korea Adv Inst Sci & Technol, Dept Nucl Engn, Taejon 305701, South Korea
关键词
D O I
10.1016/S0306-4549(00)00121-3
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
A consistent probabilistic approach is proposed to evaluate the feasibility of in-vessel retention of the molten cerium through external reactor vessel cooling (IVR-ERVC) during severe accidents of pressurized water reactors (PWRs). By combining the results of Level-1 probabilistic safety assessment, a critical heat flux correlation, and wall heat flux distributions calculated by a severe accident code with appropriate adjustment, we can reasonably predict the overall success probability of the IVR-ERVC from the viewpoint of thermal failure. The practicability of the proposed approach is illustrated with a preliminary application to the Korean Standard Nuclear Power Plant. This paper also discusses future developmental needs for more reliable assessment. (C) 2001 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码:1237 / 1250
页数:14
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