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首页> 外文期刊>Journal of Nuclear Science and Technology >APPLICATION OF PSA METHODOLOGY TO DESIGN IMPROVEMENT OF JAERI PASSIVE SAFETY REACTOR (JPSR)
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APPLICATION OF PSA METHODOLOGY TO DESIGN IMPROVEMENT OF JAERI PASSIVE SAFETY REACTOR (JPSR)

机译:PSA方法论在Jaeri被动安全反应器(JPSR)设计改进中的应用

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摘要

A probabilistic safety assessment (PSA) technique was applied to the design of JAERI Passive Safety Reactor (JPSR). A PSA was performed to clarify safety features and identify vulnerabilities of the original design. Based on the PSA results and considering thermal-hydraulic analyses and experiments, the JPSR design was improved to enhance plant safety. The improved design was re-evaluated with the PSA. Initiating events selected in this study were: large-break LOCA, medium- and small-break LOCAs, SGTR, main steam line break, loss of offsite power, loss of feed water, and other transients. Fault tree analyses were used to evaluate the system unavailabilities. The total core damage frequency due to internal events was estimated to be less than 10(-7)/RY. The contribution of high frequency non-LOCA events could be significantly reduced by the design modification. The dominant initiating event was the small break LOCA and the dominant sequence was the failure of residual heat removal system. The present study indicated that the improved JPSR design has sufficient safety margin and the PSA methodology is very effective to improve reactor safety systems in a conceptual design phase. [References: 18]
机译:概率安全评估(PSA)技术应用于JAERI被动安全反应堆(JPSR)的设计。进行了PSA,以阐明安全功能并确定原始设计的漏洞。基于PSA结果并考虑热工液压分析和实验,对JPSR设计进行了改进以提高工厂安全性。 PSA重新评估了改进后的设计。在本研究中选择的启动事件是:大中断LOCA,中中断和小中断LOCA,SGTR,主蒸汽管线中断,场外功率损失,给水损失和其他瞬变。故障树分析用于评估系统不可用性。由于内部事件造成的总核心损坏频率估计小于10(-7)/ RY。通过修改设计,可以大大减少高频非LOCA事件的影响。主导的启动事件是LOCA的小断裂,主导的顺序是残余除热系统的故障。本研究表明,改进的JPSR设计具有足够的安全裕度,而PSA方法论在概念设计阶段对改善反应堆安全系统非常有效。 [参考:18]

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