摘要
本工作耦合建立了600MW压水堆核电厂热工水力、裂变产物行为和放射性后果评价的分析模型,选取SB-LOCA、SGTR、SBO和LOFW等4个高压熔堆事故序列,研究了主回路卸压对压力容器外裂变产物释放的影响,包括主回路卸压对压力容器外裂变产物释放的缓解效应和其他负面影响。分析表明:实施主回路卸压可缓解高压熔堆事故序列下压力容器外的释放,但卸压工况下事故早期安全壳内的气载放射性活度较基准工况下的大。相关分析结论可作为严重事故管理导则制定的技术基础。
Coupling model of thermal-hydraulic,fission products behavior and radiological consequences assessment was constructed.Based on high-pressure core melt severe accidents of SB-LOCA,SGTR,SBO,and LOFW,the influence of reactor coolant system（RCS） depressurization on ex-vessel release of fission products was studied,including mitigation effect on ex-vessel release of fission products and other negative effects.It is shown that RCS depressurization can mitigate ex-vessel release of fission products for high-pressure core melt accident sequences,while airborne activity in the early phase with RCS depressurization is higher than that of the base cases without RCS depressurization.The research results can give support to establish severe accident management guideline.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2013年第7期1187-1191,共5页
Atomic Energy Science and Technology
基金
国家重点基础研究发展计划资助项目(2009CB724301)
国家自然科学基金资助项目(11075104)
关键词
主回路卸压
压力容器外释放
高压熔堆事故
缓解
负面影响
RCS depressurization
ex-vessel release
high-pressure core melt severe accident
mitigation
negative effect
