华龙一号反应堆堆腔注水冷却系统设计与安全特性研究

Dahuan Zhu,Chunrui Deng,Qing Wu,Qingan Xiang,Changwen Liu,Guijun Leng,Ming Zhang,Liqiang Hou,Xiaohua Zhang,Bin Chen,Zhonghua Guan,Lingjun Wu,Zhiqiang Zou,Xiaoji Wang,Zhen Zhang

Nuclear Power Engineering（2019）

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Abstract

华龙一号反应堆采用堆腔注水冷却系统作为严重事故的关键缓解措施,通过压力容器外部冷却实现熔融物压力容器内滞留(IVR).针对系统的安全特性开展了深入的研究论证,包括严重事故序列分析、熔融物失效迁移行为研究、临界热流密度(CHF)试验以及基于CISER程序的热工有效性论证.结果表明,华龙一号堆腔注水冷却系统(CIS)具有足够安全裕量,在严重事故下可保证压力容器的完整性.

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