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秦山核电站燃料元件考验回路PSA

A PROBABILISTIC SAFETY ASSESSMENT OF IN-PILE TEST LOOP IN HWRR

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【作者】 曹学武李兆桓

【Author】 Cao Xuewu Li Zhaohuan (China Institute of Atomic Energy, Beijing)

【机构】 中国原子能科学研究院中国原子能科学研究院 北京北京

【摘要】 秦山核电站燃料元件考验回路是为了考验秦山核电站燃料元件而设计的,它安装在重水研究堆上。运用概率安全评价方法(PSA)对考验回路进行分析,其目的是为了估价它的安全性和评价此回路的设计。分析的步骤和模式与核电站的PSA相同。主要步骤是熟悉此系统,调查和选择初因事件,建立事件树、故障树,收集数据,定性分析、定量分析和结果分析。分析仅限制在考验回路的初因及正常运行时考验回路操纵员可能的失误。分析结果:事故发生的总频率小于10-4a-1,此事故发生频率作为考验回路安全运行是可以接受的。对考验回路的设计提出改进意见,特别是关于操纵员的人因失误。

【Abstract】 The PSA methodology has been applied to the in-pile test loop which is installed in the Heavy Water Research Reactor (HWRR).This loop is designed and operated for fuel assembly testing of the Qinshan PWR plant. This analysis is to assess the safety and to evaluate the design of this operating loop. The procedure and models are similar to a PSA on nuclear power plant. The major contents in the analysis consist of the familiarization of the object,the investigation and selection of accident initiators, setting events and fault trees,data collections, quantitative calculations, qualitative and result analyses and final conclusion. This analysis is only limited to the initiators of in-pile loop itself and possible errors made by operators during normal operation. The accident occurrence is less than 10-4a-1 which may be recommended as an acceptance risk for safety operation of an in-pile test loop. Finally,suggestions have been raised to improve the design of test loop,especially in reducing operation errors by local operators.

  • 【文献出处】 中国核科技报告 ,China Nuclear Science and Technology Report , 编辑部邮箱 ,1991年S3期
  • 【被引频次】2
  • 【下载频次】63
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