摘要
针对我国二代改进型三环路核电厂乏燃料水池冷却管线破口事故(LOCA)引发的严重事故,使用MECLOR1.8.6程序进行了建模计算,分析研究了严重事故进程和乏燃料组件加热、熔化以及氢气的产生等主要现象。结果表明,乏燃料水池严重事故进程相对缓慢,但乏燃料组件的熔化及产生的氢气风险还是可能最终造成放射性向环境的大量释放。此外,本文还对乏燃料水池严重事故管理导则中的应急注水策略和氢气风险管理策略的有效性进行了计算分析,得到了严重事故下执行相关策略的时间窗口,从而为同类型核电厂严重事故管理导则的开发和有效执行提供支持。
For the improved three loops generation Ⅱ NPP,the severe accident caused by large break of spent fuel pool cooling pipe was calculated by using MECLOR1.8.6,and the progression and primary phenomena were also analyzed and researched,such as spent fuel heatup,fuel melt and hydrogen production etc.The results indicate that the severe accident process of spent fuel pool is relatively quite slow,but the spent fuel melt and hydrogen risk of combustion or detonation could still finally cause the release of radioactivity to the environment.Furthermore,the efficiencies of the emergency injection strategy and hydrogen risk management strategy used in spent fuel pool severe accident management guidelines were analyzed,the time windows of these strategies implemented during severe accident were obtained,and consequently the important support can be provided for the development and application of severe accident management guidance for similar plants.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2017年第9期1652-1657,共6页
Atomic Energy Science and Technology
关键词
乏燃料水池
严重事故
氢气风险
严重事故管理
spent fuel pool
severe accident
hydrogen risk
severe accident management