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RECOMMENDATIONS FOR CONDUCTING PROBABILISTIC RISK ASSESSMENT OF SPENT FUEL STORAGE FACILITIES

机译:进行燃油存储设施的概率风险评估的建议

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Currently, the probabilistic risk assessments (PRA) for the nuclear power plant (NPP) sites are primarily focused on the reactor counterpart. However, evoked by the 2011 Fukushima Daiichi accident, it has been widely recognized that a complete site risk profile should not be confined to the reactor units, but should cover all the radiological sources in a site, e.g. spent fuel storage facilities. During the operation of the reactor units, the used fuel assemblies will be unloaded from the reactor core to the storage facilities in a continuous or periodical manner. Accident scenarios involving such facilities can occur with non-negligible frequencies and significant consequences, posing threat to public safety. Hence, the risk contributions from such scenarios should be carefully estimated and integrated into the safety goal evaluations. The spent fuel storage facilities can be categorized as two types: pool storage units and dry cask storage facilities. In the former type, spent fuel assemblies are stored in large pools inside or outside the reactor building, with the residual heat removed by natural or forced water circulation. The latter type, where air or inert gas circulation plays an important role, appear mostly as a complementary method, along with the pool storage units, to expand the plant's storage capacity. For instance, at the Daiichi plant, there are several fuel pool units holding some fresh fuel and some used fuel, the latter awaiting for its transfer to the dry cask storage facilities on site. Note that, as well as in a joint manner, both storage facilities can be designed to serve the NPPs independently. As a fully developed method to identify potential risk in a logical and quantitative way, the framework of PRA can be generally applied to the spent fuel storage facilities with some special considerations. This paper is aimed at giving recommendations for the spent fuel storage facility PRAs, including (1) clarifying the analysis scope of risk from spent fuel storage facilities; (2) illustrating four key issues that determines such risk; (3) presenting three essential considerations when conducting PRAs to evaluate such risk. Also, this paper integrates the insights obtained from two representative case studies involving two NPP sites with different types of both fuel elements and storage facilities.
机译:当前,核电厂(NPP)场址的概率风险评估(PRA)主要集中在反应堆对应物上。但是,由2011年福岛第一核电站事故引起的人们已经普遍认识到,不应将完整的现场风险概况局限于反应堆单元,而应涵盖现场的所有放射源,例如乏燃料存储设施。在反应堆单元运行期间,用过的燃料组件将以连续或定期的方式从反应堆堆芯卸载至存储设施。涉及此类设施的事故场景可能以不可忽略的频率发生,并造成严重后果,对公共安全构成威胁。因此,应仔细估计这种情况下的风险贡献,并将其纳入安全目标评估中。乏燃料存储设施可分为两种类型:池存储单元和干桶存储设施。在前一种类型中,乏燃料组件存储在反应堆建筑物内部或外部的大水池中,剩余的热量通过自然或强制水循环除去。在后一种类型中,空气或惰性气体的循环起着重要的作用,它主要与池存储单元一起作为补充方法出现,以扩大工厂的存储容量。例如,在第一工厂,有几个燃料池单元,其中装有一些新鲜燃料和一些废燃料,后者等待将其转移到现场的干桶存储设施中。注意,以及以联合的方式,两个存储设施都可以设计为独立地服务于核电厂。作为以逻辑和定量方式识别潜在风险的全面开发方法,PRA框架通常可以应用到乏燃料存储设施中,但需要特别注意。本文旨在为乏燃料存储设施PRA提供建议,包括(1)明确乏燃料存储设施的风险分析范围; (2)说明确定此类风险的四个关键问题; (3)在进行风险评估时提出三个基本考虑因素。此外,本文还结合了从两个具有代表性的案例研究中获得的见解,这些案例研究涉及两个具有不同类型燃料元素和存储设施的核电厂。

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