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基于非参数统计法的DRM分析方法改进研究

Research on Improvement of DRM Methodology Based on Nonparametric Statistical Method
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摘要 确定现实方法(DRM)基于响应面分析方法进行不确定性评价,并在现实模型中引入保守裕度,使得最终结果包络不确定性的可信度大于95%。本文在DRM的基础上,采用独立于不确定性参数的非参数统计法代替响应面分析方法,以峰值包壳温度为目标参数,对典型3环路压水堆核电厂的大破口失水事故(LB-LOCA)进行不确定性分析,结果表明:基于非参数统计法得到的满足95%/95%概率要求的峰值包壳温度被原有DRM的计算值所包络,通过该改进方法可以获得更大的安全裕量。 The DRM methodology uses the response surface method for uncertainty analysis, and introduces a penalization mode that covers the overall calculation uncertainty, which enables estimation of PCT with a confidence level greater than 95%. In this paper, taking the PCT as the target parameter, the nonparametric statistical method was used instead of the response surface method to perform uncertainty analysis in LB-LOCA accident. It was found that, the PCT of 95%/95% level based on nonparametric statistical method was enveloped by that based on DRM methodology. © 2015, Editorial Office of Nuclear Power Engineering. All right reserved.
作者 陈伟
出处 《核动力工程》 EI CAS CSCD 北大核心 2015年第S2期112-115,共4页 Nuclear Power Engineering
关键词 大破口失水事故 非参数统计法 不确定性评价 确定现实方法 Loss of coolant accidents Statistics Surface properties Uncertainty analysis
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参考文献5

  • 1Robert P. Martin,Larry D. O’Dell.??AREVA’s realistic large break LOCA analysis methodology(J)Nuclear Engineering and Design . 2005 (16)
  • 2孙吉良.大破口失水事故的DRM分析方法介绍[J].核动力工程,2002,23(2):42-45. 被引量:5
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  • 5IAEA.Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. Safety Reports Series No.52 . 2008

二级参考文献4

  • 1[1]USNRC CFR 50-1974,Chapter 50.46: Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors Appendix K to Part 50: ECCS Evaluation Models[S].
  • 2[2]USNRC CFR 50-1980,Chapter 50.46: Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors--Appendix K to Part 50: ECCS Evaluation Models[S].
  • 3[3]USNRC Regulatory Guide 1.157-1989: Best Estimate Calculations of Emergency Core Cooling System Perfoformance[S].
  • 4[4]J Y Sauvage,Marc Ludmann.LBLOCA Analysis Using the Dterministic Realistic Methodology--Application to the 3-Loop Plant[C].7th International Conference of Nuclear Engineering,Tokyo Japan,April 19-23.1999,ICONE-7413.

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