第34卷第3期 2014年9月
核科学与工程
Nuclear Science and Engineering
非能动先进压水堆核电厂严重事故下裂变产物行为研究
袁凯，邹杰，佟立丽，曹学武（上海交通大学机械与动力工程学院，上海200240）
Vol.34No.3
Sep.2014
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，重点关注情性气体、挥发性裂变产物和非挥发性裂变产物在核电厂的分布，最终计算释人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。
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
中图分类号：TL364十，4
文章标志码：A
文章编号：0258-0918(2014)03-0382-08
AnalysisofFissionProductBehaviorsofAdvanced
PassivePWRduringSevereAccident YUAN Kai,ZOU Jie,TONG Li-li,CAO Xue-wu
(School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China)
Abstract; 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 management
收稿日期：2012-10-22；修回日期，2013-06-28
基金项目：国家重点基础研究发展计划（2009CB724301)；国家自然科学基金（11075104)
作者简介：袁凯（1979—），男，江苏泰州人，博士研究生，现从事核能科学与工程方面的工作 382