Analysis of Effect of Steam-Line Break Accident on Core of Ling'ao Unit 1 Cycle 3
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摘要: 在大亚湾和岭澳核电站近几年换料设计的安全评价中,经常出现主蒸汽管断裂(SLB)事故堆芯后果超限的情况,导致该事故需要进行再分析评价。因此,SLB事故堆芯后果分析就成为大亚湾和岭澳换料设计中重要的安全分析工作。该分析基于法马通公司的堆芯设计方法,大亚湾核电运营管理有限责任公司技术部(DNMC)针对岭澳核电站1号机组第三循环所作的换料设计,进行了主蒸汽管断裂事故堆芯后果分析。分析结果表明,在发生主蒸汽管断裂事故条件下,DNMC设计的岭澳核电站1号机组第三循环的堆芯是安全的。Abstract: In the specific reload safety evaluations in Daya Bay and Ling’ao nuclear power stations,the steam line break（SLB） accident often resulted in the core parameters exceeding the safety limits during recent years.This leads to the reanalysis of SLB accident.Therefore,the analysis of effects of SLB on core is very important in the reload design in Daya Bay and Ling’ao nuclear power stations.This paper presents the analysis of the effect of SLB on core for Ling’ao unit 1 cycle 3,based on the Framatome ANP core design procedure manual.The analytical results show that,the core designed by DMNC for Ling’ao unit 1 cycle 3 is safe,during the SLB accident.
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