风险指引的CPR1000核电厂LBLOCA分析方法初步研究
Preliminary Study on Risk-informed LBLOCA of CPR1000 Nuclear Power Plant
-
摘要: 随着核电厂安全分析方法的不断发展,结合传统确定论分析与概率风险评价(PSA)的风险指引型安全分析方法逐渐引起安审当局和核电业主的广泛关注。本文基于国际上风险指引型分析方法在其他领域的应用现状,提出了风险指引的大破口失水事故(LBLOCA)分析方法,并重新评估了CPR1000核电厂的堆芯燃料包壳峰值温度(PCT)裕量。在PSA分析中,识别并量化了LBLOCA发生后可能发生的162个事件序列,并采用确定论现实分析方法(DRM)对筛选出的18个概率较大的事件序列进行了计算分析。然后通过期望值评估法和特定序列覆盖法对LBLOCA的PCT裕量进行了评估。结果表明,本文方法下LBLOCA的PCT裕量约为36~55 ℃,相比于传统的DRM裕量提升了16~35 ℃。Abstract: With the development of the safety assessment approach of nuclear power plants (NPPs), a risk-informed analysis methodology combining traditional deterministic methodology and probabilistic safety assessment (PSA) has aroused a widespread concern in nuclear safety authorities and nuclear power plant owners. Following the international application of risk-informed analysis methodology, the framework of risk-informed large break loss of coolant accident (LBLOCA) was proposed, and the peak cladding temperature (PCT) margin of CPR1000 nuclear power plant was re-evaluated in this paper. In the PSA analysis, 162 probabilistic sequences were identified and quantified after LBLOCA occured. Then 18 probabilistically significant sequences were selected for the deterministic methodology analysis with deterministic realistic method (DRM). Then the risk-informed PCT margin was evaluated by two different methods, namely the expecting value estimation method and the sequence probability coverage method. The results show that the PCT margin evaluated by the risk-informed LBLOCA is about 36-55 ℃, which is greater than that of the DRM by 16-35 ℃.
-
-
[1] Westinghouse Company. Realistic large-break loss-of coolant accident evaluation using the automated statistical treatment of uncertainty method, WCAP-16009-p-A[R]. US: Westinghouse Company, 2005. [2] GARRICK B J, CHRISTIE R F. Probabilistic risk assessment practices in the USA for nuclear power plants[J]. Safety Science, 2002, 40(1): 177-201. [3] Nuclear Regulatory Commission. 10 CFR 50.46 Acceptance criteria for emergency core cooling systems for light water nuclear power reactors[S]. US: Nuclear Regulatory Commission, 1974. [4] Nuclear Regulatory Commission. 10 CFR 50.46a Draft final rule language—Alternative acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, ADAMS Accession No. ML 10120271[R]. US: Nuclear Regulatory Commission, 2010. [5] Nuclear Regulatory Commission. Plant-specific applicability of transition break size specified in 10 CFR 50.46a, Draft Regulatory Guide DG-1216[S]. US: Nuclear Regulatory Commission, 2010. [6] Nuclear Regulatory Commission. Risk-informed changes to loss-of-coolant accident technical requirements (10 CFR 50.46a), SECY-10-0161[R]. US: Nuclear Regulatory Commission, 2010. [7] SHERRY R R, GABOR J R, HESS S M. Pilot application of risk informed safety margin characterization to a total loss of feedwater event[J]. Reliability Engineering and System Safety, 2013, 117: 65-72. [8] DUBE D A, SHERRY R R, GABOR J R, et al. Application of risk informed safety margin characterization to extended power uprate analysis[J]. Reliability Engineering and System Safety, 2014, 129: 19-28. [9] 俞冀阳,俞尔俊. 核电厂事故分析[M]. 北京:清华大学出版社,2012. [10] LIANG T H, LIANG K S, CHENG C K, et al. Risk-informed analysis of the large break loss of coolant accident and PCT margin evaluation with the RISMC methodology[J]. Nuclear Engineering & Design, 2016, 308: 214-221. [11] Risk spectrum theory manual[M]. Relcon A B: [s. n.], 1998.
计量
- 文章访问数: 201
- HTML全文浏览量: 2
- PDF下载量: 1039