新建核电厂设计扩展工况中复杂事故序列的确定方法研究  

Determination Method of Complex Accident Sequences for New Nuclear Power Plant Design Extension Conditions

作　　者：郑华 魏淑虹 ZHENG Hua;WEI Shu-hong(China Nuclear Power Design Co.,Ltd.(Shenzhen),Shenzhen,Guangdong Prov.518000,China)

机构地区：[1]深圳中广核工程设计有限公司,广东深圳518000

出　　处：《核科学与工程》2018年第4期673-678,共6页Nuclear Science and Engineering

摘　　要：根据国际原子能机构安全要求SSR-2/1和轻水堆核电厂欧洲用户要求(EUR),新设计核电厂需要考虑设计扩展工况,包括复杂事故序列和严重事故。国内、外核安全法规和技术标准没有给出确定设计扩展工况中复杂事故序列的具体方法。本文系统分析和研究了设计扩展工况中复杂事故序列的确定方法,提出基于核安全法规、导则和技术标准要求,基于概率安全评价(PSA)的风险见解,基于工程判断和基于类似核电厂设计经验四种具体方法,并应用于防城港核电厂3号、4号机组工程设计。本方法可用于指导新建核电厂设计,合理选择复杂事故序列和开展相关的安全特征设计,以进一步提高核电厂的安全水平。New nuclear power plants shall consider design extension conditions according to IAEA safety requirements SSR-2/1 and EUR,which include complex accident sequences and severe accidents.But there are no detailed methods to determine complex accident sequences in China or international nuclear safety regulations and standards.Determination methods of complex accident sequences are analyzed systematically and four methods are proposed,including regulations and standards requirements,PSA-based method,engineering judgment,and reference to the design experience of similar nuclear power plants.This method is used and verified in the engineering design of Units 3&4 of Fangchenggang nuclear power plant.This method can be used for new nuclear power plants in determining the complex accident sequences and designing related safety features reasonably to enhance safety.

关 键 词：设计扩展工况 复杂事故序列 严重事故 确定方法 

分 类 号：TL364.1[核科学技术—核技术及应用]