摘要
用RELAP5 /MOD3 .2程序模拟了在RD 1 4实验装置上进行的两个CANDU反应堆临界破口实验。对破口出现以后 ,冷却剂系统压力、堆芯压降和元件包壳温度的变化趋势进行了研究 ,计算结果和实验数据符合较好 。
In this paper, two critical break LOCAs simuiated in RD-14 fality are analyzed with RELAP5/MOD3.2. The varieties of several important thermal-hydraulic characters, such as broken header pressure, differential pressure acrose the downstream heated section, fuel-element-simulator(FES) sheath temperature, are compared with experimental data. The consiscency between calcultd results and experimental data identifies the validity of RELAP5 in CANDU reactors, transient analysis.
出处
《核科学与工程》
CSCD
北大核心
2003年第2期118-122,160,共6页
Nuclear Science and Engineering
