Analysis of Severe Accident Scenarios for an Advanced PWR using MELCOR code
A large break LOCA scenario for an advanced power reactor 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, which is developed by Sandia National Laboratories for the U.S. NRC. The present results (the failure mode and the timing of lower head failure) would be used as input for the establishment of severe accident management strategies or for the design of core catcher of advanced power reactor. The MELCOR results showed that the lower head instrumentation tube penetration model and internal structure in the advanced reactor had influence on the amount of corium ejected and the timing of reactor vessel failure.
Advanced PWR severe accident LOCA vessel failure core catcher design MELCOR code
Tae-Woon Kim Rae-Joon Park Jin-Ho Song Sung-Won Cho
Korea Atomic Energy Research Institute 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Korea
国际会议
上海
英文
2699-2709
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）