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安全壳管道贯穿件分析评定程序的开发 被引量:2

Analysis program for SCV penetration
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摘要 核电站中存在着一类特殊的管道穿安全壳部件,即安全壳贯穿件。其分析方法与规范要求不同于管道分析。因而,针对CAP1000电站中带封头的安全壳贯穿件,需要一套方法和流程对其进行计算、分析和评定。本文以CAP1000带封头的机械贯穿件为研究对象,经分析、研究及对比,基于通用有限元软件ANSYS,以及轴对称模型非轴对称加载和既定的载荷组合策略完成计算,基于通用文档处理软件Excel完成评定,并且应用VB软件将整个计算和分析流程界面化,开发了一套针对带封头的机械贯穿件进行应力分析和疲劳分析的应用程序。本文中的分析评定方法和流程以及基于该方法而编写的程序准确、可靠,可极大地提高工作效率。 Background: Steel Containment Vessel (SCV) penetrations are special parts in nuclear plant. The analysis method and acceptance criteria of SCV penetration are different from piping. The analysis method and acceptance criteria for SCV penetration of CAP1000 plant are required. Purpose: To set the analysis method and acceptance criteria for SCV penetration. And base on these calculation and evaluation method, make a program for the penetration calculation and evaluation that is automatic, rapid and easy to use. Methods: The development of this program is based on the research and contrast. The axisymmetric penetration model with nonaxisymmetric loading is established in this program. The two sides loads combination of penetration is considered in this program. The stress is calculated by ANSYS 11.0; preprocess is developed by VB and post-process is done by Excel. Results: The analysis method and acceptance criteria of SCV penetration are established, and a program for the penetration calculation and evaluation is developed which is automatic, rapid and easy to use. Conclusions: The analysis method and acceptance criteria of SCV penetration and the program for the penetration calculation and evaluation in this paper are reliable. By this program, the high speed and accurate penetration analysis will be expected.
出处 《核技术》 CAS CSCD 北大核心 2013年第4期313-318,共6页 Nuclear Techniques
关键词 机械贯穿件 轴对称模型 非轴对称加载 应力评定 疲劳评 Penetration Axisymmetric model Nonaxisymmetric loading Stress analysis Fatigue analysis
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参考文献4

  • 1Penetration stress analysis program-penna user manual[Z],1993.
  • 2江娉婷.带封头的安全壳机械贯穿件规范书[Z].上海:上海核工程研究设计院,2011.
  • 3ASME boiler and pressure vessel code, Section III, Rules for Construction of Nuclear Facility Components[S]. 2007 Edition, 2007, NC: 40 73.
  • 4ASME boiler and pressure vessel code, Section III, Rules for Construetion of Nuclear Facility Components[S]. 2007 Edition, 2007, NE: 43-61.

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