摘要
在模块式小型堆MELCOR分析模型的基础上,对典型严重事故序列进行计算分析,得到压力容器下腔室内堆芯熔融池特征参数,并使用自主研发的CISER程序对模块式小型堆堆腔注水冷却效果进行研究。通过影响参数的敏感性及保守性分析证明模块式小型堆堆腔注水冷却措施可行且有适当的安全裕量。
Typical severe accident scenarios are calculated to obtain the characteristic parameters of the molten pool in the lower vessel plenum, based on the MELCOR model for small module reactors. The indigenous CISER code is then used to analyze and validate the effectiveness of the cavity injection and cooling strategy for the small module reactors, considering conservatively the issues of phenomenological uncertainties.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2015年第1期165-167,共3页
Nuclear Power Engineering