Assessment of the COBRA/RELAP5 code using the LOFT L2-3 large-break loss-of-coolant experiment

被引:15
作者
Jeong, JJ
Sim, SK
Ban, CH
Park, CE
机构
[1] KOREA NUCL FUEL CO LTD,TAEJON 305600,SOUTH KOREA
[2] KOREA POWER ENGN CO INC,TAEJON 305600,SOUTH KOREA
关键词
D O I
10.1016/S0306-4549(97)00029-7
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
The COBRA/RELAP5 code, a merged version of COBRA-TF and RELAP5/MOD3 5m5, was upgraded with RELAP5/MOD3.2. Using the ''inter-process communication'' technique, the realistic three-dimensional reactor vessel module of CIBRA-TF was linked with the RELAP5 code in the merged code. The three-dimensional capability of COBRA/RELAP5 was assessed using the LOFT L2-3 large-break loss-of-coolant accident (LOCA) experimental data. The evaluate the overall performance of the code, relatively fine three-dimensional meshes were used for the reactor vessel, which was simulated by CIBRA-TF, and the other systems were one-dimensionally modeled by RELAP5/MOD3.2. The simulation results showed that COBRA/ RELAP5 is a promising tool for analysis of complicated, multidimensional, two-phase flow transients in pressurized water reactors (PWRS). (C) 1997 Elsevier Science Ltd.
引用
收藏
页码:1171 / 1182
页数:12
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