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多堆厂址始发事件分析探讨

Analysis and Discussion on Initial Event of Multi-unit
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摘要 多堆厂址一级概率安全评价(PSA)研究中,机组数目的增加使得建模工作量剧增,给整个核电厂的风险评估带来困难。结合已有基础,本文研究了多堆厂址始发事件分析的筛选方法,提出利用堆芯损伤频率(CDF)上下限值评估方法,分析厂址内不同机组数对厂址CDF的影响。结果表明,双机组厂址适合优先进行具体分析。针对双机组核电站,对多堆厂址内各始发事件进行筛选。结果表明,丧失厂外电、丧失热阱等事件适合建模分析,并对其他筛选结果给出后续分析建议,为多堆厂址一级PSA后续事故序列建模工作提供了重要基础。 In the multi-unit level 1 probabilistic safety assessment(PSA)study,the modeling workload greatly increases due to the increase of the number of units,which brings difficulties to the risk assessment of the whole nuclear power plants.Based on the existing foundation,the method for preliminary evaluation of initiating event consequences in a site was studied in this paper.The calculation method of core damage frequency(CDF)upper and lower bounds was used to analyze the influence of the number of units on CDF in the site.The results show that the two-unit site is suitable for priority analysis.In view of the dual-unit site,the initial events within the multi-unit site were screened.The results show that the loss-of-offsite-power(LOOP),loss of heat trap and other events are suitable for modeling and analysis.Recommendations were also made for other screening results.This paper provides an important basis for the modeling of the level 1 PSA subsequent accident sequence at multi-unit sites.
作者 冯琬昕 徐志新 玉宇 刘灌钰 彭礼韬 FENG Wanxin;XUN Zhixin;YU Yu;LIU Guanyu;PENG Litao(State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment,China Nuclear Engineering Co.,Ltd.,Shenzhen 518172,China;Beijing Key Laboratory of Passive Safety Technology for Nuclear Energy,North China Electric Power University,Beijing 102206,China;School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China)
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2021年第11期2043-2047,共5页 Atomic Energy Science and Technology
关键词 多机组核电厂 概率安全评价 始发事件 堆芯损伤 multi-unit nuclear power plant probabilistic safety assessment initial event core damage
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  • 1中华人民共和国环境保护部.GB6249-2011核动力厂环境辐射防护规定[S].北京:中华人民共和国环境保护部,2011.
  • 2NRC. Safety goals for the operations of nuclear power plants, 51FR30028[R]. US: NRC, 1986.
  • 3KARL N F. On the issue of integrated risk: A PRA practitioners perspective [R/OL]. (2011- 11-10). http://www, nrc. gov.
  • 4刘涛,童节娟,赵军.一址多堆核电厂的概率安全分析讨论[C]//2012核能概率安全分析(PSA)研讨会会议文集.上海:中国核能行业协会,2012.
  • 5ASME. ASME/ANS RA-Sa--2009 Standard for level 1: Large early release frequency proba- bilistic risk assessment for nuclear power plant applications[S]. US: ASME, 2009.
  • 6NRC. An approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities, RG 1. 200[R]. US: NRC, 2009.

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