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基于概率安全评价的CPR1000核电厂台风情况下运行控制策略研究

Study on the Operation Control Strategy of CPR1000 Nuclear Power Plant under Typhoon Condition Based on Probabilistic Safety Assessment
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摘要 台风是核电厂面临的主要外部灾害之一,威胁机组的安全稳定运行。当前国内核电厂普遍缺乏台风情况下以保障核安全为目标的机组控制手段,仅依靠运行经验和电网要求开展决策,未针对台风的影响开展详细的分析和论证。为解决该问题,本文采用概率安全评价方法,以CPR1000机组为分析对象,对核电厂台风情况下的运行控制策略进行分析和论证。针对台风导致的核电厂事故,定量评价不同机组运行模式下的风险水平。结果表明,具备RRA运行条件的NS/SG模式是风险最低的机组后撤状态。在此基础上,结合核电厂实际的运行特点,提出建议的机组运行控制行动。本文的分析可为核电厂台风情况下机组控制策略的制定提供理论依据和技术参考。 Typhoon is one of the main external disasters of nuclear power plant,which is a risk to nuclear safety and plant operation.At present,nuclear power plant lacks the operation control strategy to ensure nuclear safety under typhoon condition,and only rely on operation experience and power grid requirements to make decisions.In order to solve this problem,taking CPR1000 as an example,a study on the operation control strategy of nuclear power plant under typhoon condition using the probabilistic safety assessment method is carried out in this paper.The risk of different operation modes is quantitatively analyzed for accidents caused by typhoon.The results show that the risk of the NS/SG mode with the RRA connection condition is the lowest.According to the operation characteristics of nuclear power plant,an operation control strategy is recommended.The analysis in this paper can provide theoretical basis and technical reference for the operation control strategy of nuclear power plant under typhoon condition.
作者 冯丙辰 王晗丁 杨志超 沈荣发 FENG Bingchen;WANG Handing;YANG Zhichao;SHEN Rongfa(Suzhou Nuclear Power Research Institute,Shenzhen of Guangdong Prov.518000,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2023年第3期699-704,共6页 Nuclear Science and Engineering
关键词 台风 概率安全评价(PSA) 运行控制 核电厂 Typhoon Probabilistic safety assessment(PSA) Operation control Nuclear power plant
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  • 1王朝贵,郭建兵.大亚湾核电站全厂断电事故及第5台应急柴油机的概率安全评价[J].核动力工程,2004,25(4):324-327. 被引量:12
  • 2谢强,李杰.电力系统自然灾害的现状与对策[J].自然灾害学报,2006,15(4):126-131. 被引量:197
  • 3张龙飞,张大发,王少明.压水堆核电站全厂断电事故及辅助给水系统的缓解能力研究[J].核动力工程,2007,28(3):98-102. 被引量:6
  • 4SEHGAL B R, KARBOJIAN A, GIRI A, et al. Assessments of reactor vessel integrity (ARVI) [J]. Nuclear Engineering and Design, 2005, 235 : 213-232.
  • 5VIEROW K, LIAO Y, JOHNSON J, et al. Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes[J]. Nuclear Engineering and Design, 2004, 234: 129-145.
  • 6KNUDSON D L, REMPE J L, CONDIE K G, et al. Late-phase melts conditions affecting the potential for in-vessel retention in high power reactors [J]. Nuclear Engineering and Design, 2004, 230: 133-150.
  • 7Severe accident risks: An assessment for five U. S. nuclear power plants, NUREG-1150 [R]. Idaho: USNRC, 1990.
  • 8KRIEG R, DEVOS J, CAROLI C, et al. On the prediction of the reactor vessel integrity under severe accident loading(RPVSA)[J]. Nuclear Engineering and Design, 2001, 209: 117-125.
  • 9MARUYAMA Y, MORIYAMA K, NAKAMURA H, et al. Modeling for evaluation of debris coolability in lower plenum [ J ]. Nuclear Science and Technology, 2003, 40(1) : 12-21.
  • 10国家气候中心.全国气候影响评价[M].北京:气象出版社,1996..

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