非能动先进压水堆核电厂严重事故下裂变产物行为研究  

Analysis of Fission Product Behaviors of Advanced Passive PWR during Severe Accident

作　　者：袁凯[1] 邹杰[1] 佟立丽[1] 曹学武[1] 

机构地区：[1]上海交通大学机械与动力工程学院,上海200240

出　　处：《核科学与工程》2014年第3期382-389,共8页Nuclear Science and Engineering

基　　金：国家重点基础研究发展计划(2009CB724301);国家自然科学基金(11075104)

摘　　要：非能动先进压水堆核电厂在严重事故下,安全壳可能发生失效,导致大量放射性物质向环境释放。本文针对非能动先进压水堆核电厂可能发生的早期失效、中期失效、晚期失效三种释放类别,建立百万千瓦级非能动先进压水堆的事故分析模型,分别针对自动卸压系统第二级卸压阀误开启,DVI管线上发生当量直径为4英寸的破口,以及热管段发生当量直径为2英寸的破口的典型严重事故序列,在研究事故进程的基础上,分析事故下裂变产物释放和迁移的特性,重点关注惰性气体、挥发性裂变产物和非挥发性裂变产物在核电厂的分布,最终计算释入环境的裂变产物源项。本文分析结果可为严重事故管理以及厂外放射性后果评价提供支持。The containment of advanced passive PWR nuclear power plant may be out of function leading to large release to environment. The accident analysis model of advanced passive PWR was established and three release categories （ early, intermediate, late containment failure） were analyzed by using integrated safety analysis code. On the basis of analyzing three typical severe accidents （one valve of automatic depressurization system stage 2 spuriously open, 4-inch direct vessel injection line break, 2-inch hot-leg break）, the character including release and transport were analyzed. The distribution of inert gases, volatile fission products and nonvolatile fission products were focused. The source term released to environment was computed. The analyzed results of this paper may give some support for severe accident managementand assessment of the accident consequences.

关 键 词：非能动先进压水堆 严重事故 源项 挥发性裂变产物 非挥发性裂变产物 

分 类 号：TL364.4[核科学技术—核技术及应用]