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核电厂备用系统可靠性模型及其参数评估方法

Standby System Reliability Model of the Neclear Power Plant and Its Parametric Evaluation Methods
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摘要 由于同时存在备用应力和需求应力,导致了备用设备可靠性模型的多样化。本文首先给出了只考虑备用失效和需求失效的基本模型,并对在可靠性和风险评估中使用不同模型所带来的差异进行了研究,总结了两种基本模型的特点;然后,对同时考虑两种应力的综合模型的表达形式和适用性进行了分析,并提出上述三个模型的基本使用原则;最后,针对目前核电厂可靠性数据(包括通用数据库和特定核电厂的典型数据)的积累现状,对模型参数的评估方法进行了研究,提出了基于三个不同层次的数据评估方法,简要介绍了每种评估方法的实施步骤和注意事项,并在此基础上,结合中国核电厂可靠性数据的实际情况,提出了中国核电厂备用设备可靠性模型和参数评估方法的使用建议,认为在目前情况下,中国核电厂应该尽可能利用已经积累的电厂典型数据以反映中国电厂的实际情况。 Because a standby equipment is affected by the demand stress and the standby stress simultaneously, its reliability model can take various shapes. This paper first discusses two important models--the standby failure model and the demand failure model. The differences of their assessment of reliability and risk are analyzed to show the characteristics of these two models. Then, an expression considering both the standby stress and the demand stress is proposed, together with its applications, and it is discussed in three aspects. Three evaluating methods for the model parameters are related to the fact that the reliability data include both generic data and special data, The integrated model and the evaluating methods of its parameters are used in evaluating domestic nuclear power plants, where the specific data must be used as much as possible, in order to reflect the realistic states of plants.
出处 《科技导报》 CAS CSCD 北大核心 2010年第3期24-28,共5页 Science & Technology Review
关键词 备用设备 备用应力 需求应力 可靠性数据 参数评估 standby equipment standby stress demand stress reliability data parameter evaluation
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参考文献11

  • 1Lofgren E V, Thaggard M. Analysis of standby and demand stress failures modes, NUREG/CR-5823[R]. Washington DC: Division, 1992.
  • 2Houghton J R, Hamzehee H G. Component performance study-turbinedriven pumps, 1987-1998, NUREG-1715, Vol. 1 [R]. Washington DC: Division of Risk Analysis and Application Office of Nuclear Regulatory Research US Nuclear Regulatory Commission, 2000.
  • 3Houghton J R, Hamzehee H G. Component performance study-motordriven pumps, 1987-1998, NUREG-1715, Vol. 2 [R]. Washington DC: Division of Risk Analysis and Application Office of Nuclear Regulatory Research US Nuclear Regulatory Commission, 2000.
  • 4Houghton J R, Hamzehee H G. Component performance study-airoperated valves, 1987-1998, NUREG-1715, Vol. 3 [R]. Washington DC: Division of Risk Analysis and Application Office of Nuclear Regulatory Research US Nuclear Regulatory Commission, 2000.
  • 5Houghton J R, Hamzehee H G. Component performance study-motoroperated valves, 1987-1998, NUREG-1715, Vol, 4 [R]. Washington DC: Division of Risk Analysis and Application Office of Nuclear Regulatory Research US Nuclear Regulatory Commission, 2000.
  • 6Atwood C L, La Chance J L, Martz H F, et al. Handbook of parameter estimation for probabilistic risk assessment, NUREG/CR-6823 [R]. Washington DC: Division of Risk Analysis and Application Office of Nuclear Regulatory Research US Nuclear Regulatory Commission, 2003.
  • 7Lofgren E V. Time-independent and time-dependent contributions to the unavailability of standby safety system components, BNL-NUREG-64255 [R]. 1997.
  • 8Jain M, Sharma G C, Sharma R. Performance modeling of state dependent system with mixed standbys and two modes of failure [J]. Applied Mathematical Modeling, 2008, 32: 712-724.
  • 9Subramanian R, Anantharaman V. Reliability analysis of a complex standby redundant system [J]. Reliability Engineering and System Safety, 1995, 48: 57-70.
  • 10Yearout R D, Reddy P I, Grosh D L. Standby redundancy in reliability--A review [J]. IEEE Transactions on Reliability, 1986, R-35 (3): 285-292.

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