Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code

被引：16

作者：

Kim, Tae Woon ^{[1
]}

Song, Jinho ^{[1
]}

Huong, Vo Thi ^{[1
,2
]}

Kim, Dong Ha ^{[1
]}

Rhee, Bo Wook ^{[1
]}

Revankar, Shripad ^{[3
]}

机构：

[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea

[2] Univ Sci & Technol, Taejon, South Korea

[3] Purdue Univ, Sch Nucl Engn, W Lafayette, IN 47907 USA

来源：

NUCLEAR ENGINEERING AND DESIGN | 2014年 / 269卷

关键词：

D O I：

10.1016/j.nucengdes.2013.08.022

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 LBLOCA scenario for an advanced pressurized water reactor, call APR1400, developed in Korea is analyzed in order to obtain an overall insight into a severe accident progression from an initiating event to the reactor vessel failure in detail by using the MELCOR computer code Versions 1.8.5 and 1.8.6. The present results (the amount of molten corium and vessel failure timing) would be used as input for the establishment of severe accident management strategies or for the design of a core catcher for the APR1400. The MELCOR results showed that the lower head instrumentation tube penetration failure model and internal structure in the reactor vessel had influence on the amount of corium ejected and the timing of reactor vessel failure. (C) 2013 Elsevier B.V. All rights reserved.

引用

页码：155 / 159

页数：5