• CN：11-2187/TH
  • ISSN：0577-6686
机械工程学报

机械工程学报 ›› 2015, Vol. 51 ›› Issue (20): 67-78.doi: 10.3901/JME.2015.20.067

• 材料科学与工程 • 上一篇    下一篇

承压热冲击下反应堆压力容器的概率评定进展与案例分析

高增梁1,2, 李曰兵1,2, 雷月葆1,2   

  1. 1.浙江工业大学化工机械设计研究所 杭州 310032;
    2.浙江工业大学过程装备及其再制造教育部工程研究中心 杭州 310032;
  • 出版日期:2015-10-15 发布日期:2015-10-15
  • 基金资助:
    国家自然科学基金(51205356)和浙江省公益类重点(2014C23001)资助项目

Progress and Case Study on Probabilistic Assessment of Reactor Pressure Vessels under Pressurized Thermal Shock

GAO Zengliang1,2, LI Yuebing1,2, LEI Yuebao1,2   

  1. 1.Institute of Process Equipment & Control Engineering, Zhejiang University of Technology, Hangzhou 310032;
    2.Engineering Research Center of Process Equipment and Re-manufacturing of Ministry of Education, Zhejiang University of Technology, Hangzhou 310032
  • Online:2015-10-15 Published:2015-10-15

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摘要： 在压水堆核电站运行中，某些工况可能会使反应堆压力容器(Reactor pressure vessels, RPV)经受承压热冲击(Pressurized thermal shock, PTS)瞬态，这给含缺陷RPV的结构完整性带来了一定的挑战。简要介绍含缺陷RPV在PTS条件下的筛选准则及其结构完整性评定方法，重点阐述PTS下含缺陷RPV的概率评定方法。概率评定方法采用概率断裂力学(Probabilistic fracture mechanics, PFM)分析，主要内容包括不确定因素统计分析(裂纹检出率、裂纹尺寸、材料性能等)、裂纹启裂模型及穿透模型等。此外，还对适用于PTS分析的典型PFM程序进行评价。在此基础上，针对典型RPV利用自主开发的PFM程序进行两个典型PTS瞬态的案例分析和结构完整性评定。分析结果表明在60年设计寿命内分析瞬态下该RPV的失效频率低于核安全要求值。结合目前我国核电发展，针对PTS下RPV结构完整性概率评定提出几点建议。

关键词: 承压热冲击, 反应堆压力容器, 概率断裂力学, 结构完整性评定

Abstract: A certain type of transients may cause the pressurized thermal shock(PTS) in the reactor pressure vessels(RPV) in pressurized water reactors(PWR) and may result in problem of structural integrity of RPV with flaws. The structural integrity assessment methods for RPV under PTS conditions are reviewed. The research progress and situation about these methods, especially probabilistic assessment, are introduced. Probabilistic assessment which uses the probabilistic fracture mechanics(PFM) analysis approach is reviewed, including uncertainty analysis (probability of detection, flaw characterization models, fracture property data, et al.), numerical calculating method on the failure probability, et al. Main PFM computational computer codes for PTS are evaluated. A PFM program is developed to calculate the failure probability. Two typical PTS transients for RPV and their structural integrities are analyzed. The results show that the failure probability for the RPV under these PTS transients is lower than the required value of nuclear safety for the design life of 60 years. Combined with Chinese nuclear power development, a few pieces of advices are proposed for probabilistic assessment of RPV structural integrity under PTS transients.

Key words: pressurized thermal shock, probabilistic fracture mechanics, reactor pressure vessels, structural integrity assessment

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