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核电厂压力容器安全评估的新方法——主曲线简介 被引量:13

New Method of Safety Assessment for Pressure Vessel of Nuclear Power Plant-Brief Introduction of Master Curve Approach
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摘要 新的主曲线方法对反应堆压力容器完整性的评估在美国被称为革命性的改进。本文从保证核电安全的反应堆运行限值曲线出发,说明主曲线的由来、根据和标准;从对微观组织很敏感的脆性断裂特点,阐述主曲线的理论和它的统计规律性及其Weibull分布统计模型和实验方法;从断裂韧性数据库对该模型的拟合式,理解主曲线的含义、优点和应用以及主曲线的重要性和它与核电安全的关系。 The new Master Curve Method is called as a revolutionary advance to the assessment of reactor pressure vessel integrity in USA. This paper explains the origin, basis and standard of the Master Curve from the reactor pressure-temperature limit curve which assures the safety of nuclear power plant. According to the characteristics of brittle fracture which is greatly susceptible to the microstructure, the theory and the test method of the Master Curve as well as its statistical law which can be modeled using Weibull distribution are described in this paper. The meaning, advantage, application and importance of the Master Curve as well as the relation between the Master Curve and nuclear power safety are understood from the fitting formula for the fracture toughness database by Weibull distribution model.
作者 杨文斗
出处 《核安全》 2011年第2期7-13,29,共8页 Nuclear Safety
关键词 反应堆压力容器 脆性断裂 韧、脆转变温度 主曲线参考温度T_0 Weibull分布统计模型及其参数 reactor pressure vessel brittle fracture ductile-brittle transition temperature MasterCurve reference temperature To Weibull distribution statistical model and parameters
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参考文献12

  • 1Sokolov M Aet al.Use of Precracked Charpy and Smaller Specimens to Establish the Master Curve. ASTM STP 1329 . 1998
  • 2William L Set al.Technical Basis for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity Assessment. ASTM STP 1366 . 2000
  • 3ASME Boiler and Pressure Vessel Code,Code Cases N-629 Section XI. . 1999
  • 4Mark Kirket al.0</sub> Values Determined Using ASTM Standard E1921-97 for Nuclear Reactor Pressure Vessel Steels&amp;sid=ASTM STP 1366&amp;aufirst=Mark Kirket al');&#xA; ">Bias and Precision of T<sub>0</sub> Values Determined Using ASTM Standard E1921-97 for Nuclear Reactor Pressure Vessel Steels. ASTM STP 1366 . 2000
  • 5G Robert Odetteet al.Radiation Emberittlement Trend Curves and the Impact on Nuclear Plant Operating Criteria. ASTM STP 1101 . 1989
  • 6William L Set al.Development of International Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity. ASTM STP 1447 . 2003
  • 7Mikhail A Set al.Comparison Irradiation Induced Shifts of K_ (JC) and Charpy Impact Toughness for Reactor Pressure Vessel Steels. ASTM STP 1325 . 1999
  • 8Marla Set al.Master Curve of Irradiated JRQ Material. ASTM STP 1447 . 2004
  • 9Wallin,K.The scatter in KIC results. Engineering Fracture Mechanics . 1984
  • 10K Wallin.The size effect in K Ic results. Engineering Fracture Mechanics . 1985

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