摘要
华龙一号反应堆采用堆腔注水冷却系统作为严重亊故的关键缓解措施,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,包括严重亊故序列分析、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,在严重亊故下可保证压力容器的完整性。
Cavity Injection and Cooling System(CIS)is adopted as main severe accident mitigation measure for HPR1000,which is to realize In-Vessel Retention(IVR)strategy by ex-vessel cooling.Safety characteristics of CIS is investigated in detail,including the analysis of severe accident sequence,core melt relocation behavior and critical heat flux,and the thermal effectiveness demonstration with CISER code.The results indicate that there is enough safety margin for HPR1000 CIS design,and the RPV integrity can be maintained under severe accident.
作者
朱大欢
邓纯锐
吴清
向清安
刘昌文
冷贵君
张明
侯丼强
张晓华
陈彬
关仲华
武铃珺
邹志强
王小吉
张震
Zhu Dahuan;Deng Chunrui;Wu Qing;Xiang Qingan;Liu Changwen;Leng Guijun;Zhang Ming;Hou Liqiang;Zhang Xiaohua;Chen Bin;Guan Zhonghua;Wu Lingjun;Zou Zhiqiang;Wang Xiaoji;Zhang Zhen(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2019年第A01期32-36,共5页
Nuclear Power Engineering
