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作 者:伍建辉 周俊 邹春燕[1,2,3] 贾国斌[1,2] 张奥 蔡翔舟 陈金根 WU Jianhui;ZHOU Jun;ZOU Chunyan;JIA Guobin;ZHANG Ao;CAI Xiangzhou;CHEN Jingen(Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China;CAS Innovative Academies in TMSR Energy System,Chinese Academy of Sciences,Shanghai 201800,China;University of Chinese Academy of Sciences,Beijing 100049,China)
机构地区:[1]中国科学院上海应用物理研究所,上海201800 [2]中国科学院先进核能创新研究院,上海201800 [3]中国科学院大学,北京100049
出 处:《核技术》2022年第6期101-110,共10页Nuclear Techniques
基 金:国家重点研发计划项目(No.2020YFB1901900)资助。
摘 要:氦氙冷却反应堆可采用一体化布雷顿循环系统,在小型化、轻量化方面具有独特优势而备受关注。但目前鲜有关于小型氦氙冷却反应堆的严重事故分析研究。概率安全评价法(Probabilistic Safety Assessment,PSA)是一种评价反应堆安全性的重要方法,可为反应堆设计改进、故障诊断、运行指导等提供有价值的依据。而始发事件发生频率是PSA分析所必需的输入参数。本文以小型氦氙冷却移动式固体核反应堆电源为分析模型,参考高温气冷堆以及压水堆运行经验及部件失效数据,分析了堆芯排热增减、反应性和功率分布异常、管道破口和设备泄漏异常、未能紧急停堆的预期瞬态(Anticipated TransientWithoutScram,ATWS)以及丧失场外电源等事故的发生频率,结果分别为3.90×10^(−2)RY^(−1)、2.36×10^(−1)RY^(−1)、2.69×10^(−2)RY^(−1)、6.50×10^(−2)RY^(−1)、2.69×10^(−2)RY^(−1)以及4.60×10^(−2)RY^(−1),分析结果为进一步开展核电源PSA分析提供基础参考价值。[Background]Helium-xenon gas cooled nuclear reactor adopts helium-xenon gas as the coolant and is able to apply the integral Brayton cycle.It has advantages in miniaturization and lightweight design,which has attracted more and more attention worldwide.But rare severe accidents studies have been carried out for the small helium-xenon gas cooled reactor.Probabilistic safety assessment(PSA)is an important method to evaluate the safety of a reactor system.The results obtained by PSA can provide a valuable basis for improving the core design,identifying fault,guiding operation,etc.whilst the occurrence frequency of initial events is required for PSA analysis.[Purpose]This paper aims to evaluate the accident occurrence frequency for the small helium-xenon gas cooled reactor to provide an input for PSA analysis.[Methods]Based on the main technical characteristics of a small innovation helium-xenon cooled mobile nuclear power system(SIMONS),the occurrence frequency of typical accidents was analyzed by referring to the operational experiences and data of high temperature gas cooled reactor(HTGR)and light water reactor(LWR).Intensity analyses were performed on the frequency of accidents such as increase or decrease of core heat removal,abnormal reactivity and power distribution,pipe break and abnormal equipment leakage,anticipated transient without scram(ATWS),and loss of offsite power(LOOP).[Results]The calculation results show that the accidents of heat removal increase and decrease,abnormal reactivity and power distribution,pipe break and abnormal equipment leakage,ATWS,and LOOP have an occurrence frequency of 3.90×10^(−2)RY^(−1),2.36×10^(−1)RY^(−1),2.69×10^(−2)RY^(−1),6.50×10^(−2)RY^(−1),2.69×10^(−2)RY^(−1)and 4.60×10^(−2)RY^(−1),respectively.[Conclusions]The calculated results can be taken as the inputs for the PSA study of the SIMONS,providing basic reference value for further PSA analysis of mobile nuclear power system.
关 键 词:小型氦氙冷却反应堆电源 事故概率安全分析 故障树
分 类 号:TL329[核科学技术—核技术及应用]
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