Rod ejection accident (REA);
RELAP5;
VVER-1000;
FSAR;
PLANT;
D O I:
10.1016/j.anucene.2012.02.018
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:
In this study, the RELAP5 Mod3.2 code has been used to analyze the REA in a VVER-1000 reactor. For a conservative simulation, a 58 mm break is considered in the upper head of the reactor pressure vessel due to the impact of an ejected rod. Four cases, 104% of nominal power and 0.45$ of inserted reactivity, 71% of nominal power and 0.47$ of inserted reactivity, 54% of nominal power and 0.6$ of inserted reactivity, and 1% of nominal power and 0.9$ of inserted reactivity are the initial conditions. The relative power, pressure in the pressurizer, mass flow rate via break point, BRU-A performance, and fuel surface temperature are the investigated parameters. The results of the RELAP5 code are consistent with VVER-1000 FSAR data. (c) 2012 Elsevier Ltd. All rights reserved.