Selection of Complex Accident Sequences for Sodium-Cooled Fast Reactor Design Extension Conditions

Jingke Jiang, Nanfei Zhao, D. Yang
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Abstract

Design Extension Conditions (DEC) are accident conditions beyond design basis for nuclear power plants, including complex accident sequences (DEC-A) and severe accidents (DEC-B). As required by the nuclear safety regulation HAF102-2016, DEC must be considered by identifying additional accident scenarios and develop practical prevention and mitigation measures for such accidents in design process for nuclear power plants. The aim is to enhance nuclear power plant’s response to beyond design basis accidents or multi-fault accident. It’s to contribute to increase the design requirements and expand the design consideration for nuclear power plants to consider DEC in design process, which may increase the design difficulty and construction and operation costs for nuclear power plants. The selection of DEC is great significance to balance the safety and economy for nuclear power plants. Compared with DEC-B, the DEC-A is a newer concept, and the mature cognition of DEC-A has not yet been reached. The selection method of DEC-A for sodium-cooled fast reactor is analyzed systematically, which includes how to define, identify and screen DEC-A. Taking a sodium-cooled fast reactor as an example, DEC-A are identified and screened in the method of the combination of probabilistic safety assessment, determinism and engineering experience, and the entire selection process of DEC-A is performed. Besides, It is analyzed and discussed about the application of DEC-A in safety analysis and safety design of sodium-cooled fast reactors. Existing study results will provide theoretical reference for determining DEC-A lists for similar reactors.
钠冷快堆设计扩展条件下复杂事故序列的选择
设计延伸条件(DEC)是指核电厂在设计基础之外的事故条件,包括复杂事故序列(DEC- a)和严重事故(DEC- b)。根据核安全法规HAF102-2016的要求,核电厂在设计过程中必须通过确定额外的事故情景并制定切实可行的预防和缓解措施来考虑DEC。目的是提高核电站对超出设计基础事故或多故障事故的响应能力。在设计过程中考虑DEC有助于提高核电站的设计要求,扩大核电站的设计考虑范围,这可能会增加核电站的设计难度和建设运营成本。核电机组DEC的选择对于平衡核电厂的安全性和经济性具有重要意义。与DEC-B相比,DEC-A是一个较新的概念,对DEC-A的认知尚未成熟。系统地分析了钠冷快堆中deca的选择方法,包括deca的定义、鉴定和筛选。以某钠冷快堆为例,采用概率安全评估、确定性和工程经验相结合的方法对deca进行了识别和筛选,并对deca进行了整个选择过程。此外,还对deca在钠冷快堆安全分析和安全设计中的应用进行了分析和讨论。现有的研究结果将为同类反应器的deca清单的确定提供理论参考。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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