软件PIPESTRESS在核级管道应力分析中的应用
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- 英文论文题名：Application of PIPESTRESS software in stress analysis for nuclear grade pipe
- 论文作者：田欣鹭 ; 李铁萍 ; 刘锐
- 英文论文作者：TIAN Xin-lu ; LI Tie-ping ; LIU Rui ; Nuclear and Radiation Safety Center
- 年：2015
- 作者机构：环境保护部核与辐射安全中心;
- 论文关键词：PIPESTRESS ; 核级管道 ; 应力分析 ; ASME
- 英文论文关键词：PIPESTRESS ; nuclear grade pipe ; stress analysis ; ASME
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第10册（核安全分卷）
- 语种：中文
- 分类号：TM623
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：6
- 文件大小：262k
- 原文格式：O
- 会议级别：全国
摘要
PIPESTRESS软件是针对管道系统进行力学计算和分析的专业软件,融合了ASME、RCC-M等各种规范,主要用于核或非核级管道系统的设计计算和校核分析,工作过程包括建模、计算和后处理。PIPESTRESS可用于核与非核工业的三维分析,并具有对结构、支撑(支吊架)、热、疲劳等全面分析的功能。在西屋、AREVA、EDF等公司都有广泛应用。本文以某核电站核2级管道系统为分析模型,应用PIPESTRESS软件,对管道承受的自重、热膨胀、地震等载荷进行计算,计算各种载荷工况下的应力结果。选用ASME设计标准进行静力评定,得到了不同载荷组合情况下的最大应力及最高应力比,结果表明,该系统中的管段能满足ASME标准规定的限值要求。应用PIPESTRESS软件进行应力分析与评定,不仅可以保证管道系统的安全,而且可以优化设计,在核电厂的建造和运行中起到重要作用。
PIPESTRESS is professional software for mechanical calculation and analysis.Containing standard such as ASME、RCC-M、EN,it can be used in nuclear grade or non-nuclear grade design and check analysis with modeling,calculating and post-analysis module.As used widely in Westinghouse,AREVA and EDF companies,PIPESTRESS can be applied to three-dimensional calculation of structure,supported facility for heat or fatigue analysis.With application of PIPESTRESS software,the nuclear piping system in the nuclear power plant was used as an analysis model to calculate the weight,thermal expansion,seismic and so on.The selection of ASME design standard was used for static evaluation,through the calculation,the stress and the maximum stress ratios under the condition of different stress combinations were gotten.The results were shown that,some parts of the system could meet the ASME standard limit requirements.Stress analysis and evaluation by the application of PIPESTRESS software,which can not only ensure the safety of the pipeline system,and also can optimize the design.The software was played an important role in the construction and operation of a nuclear power plant.
PIPESTRESS is professional software for mechanical calculation and analysis.Containing standard such as ASME、RCC-M、EN,it can be used in nuclear grade or non-nuclear grade design and check analysis with modeling,calculating and post-analysis module.As used widely in Westinghouse,AREVA and EDF companies,PIPESTRESS can be applied to three-dimensional calculation of structure,supported facility for heat or fatigue analysis.With application of PIPESTRESS software,the nuclear piping system in the nuclear power plant was used as an analysis model to calculate the weight,thermal expansion,seismic and so on.The selection of ASME design standard was used for static evaluation,through the calculation,the stress and the maximum stress ratios under the condition of different stress combinations were gotten.The results were shown that,some parts of the system could meet the ASME standard limit requirements.Stress analysis and evaluation by the application of PIPESTRESS software,which can not only ensure the safety of the pipeline system,and also can optimize the design.The software was played an important role in the construction and operation of a nuclear power plant.
引文
[1]陈敏,张周红,吴高峰,等.APA软件在核级管系力学分析中的应用[J].华电技术,2010,32(6):38-41.
[2]唐永进.压力管道应力分析的内容及特点[J].石油化工设计,2008,25(2):20-24.
[3]陈敏,张周红.复杂管道应力分析中的支吊架布置方法[J].压力容器,2009,26(3):21-25.
[4]赵艳梅,张文格,王冰.压力管道应力分析的一般途径与可靠性讨论[J].压力容器,2001,18(4):61-63.
[5]刘锐,李铁萍,张春明.基于RCC-M与ASME的核2/3级管道应力评定比较[J].压力容器,2013,30(3):52-56.
[6]RCC-M(2002 edition+2002 add),Design and Construction Rules for Mechanical Components of PWR Nuclear Islands[S].
[7]戴守通,汪军,韩治.中国先进研究对主回路出堆管接管载荷优化分析[J].原子能科学技术,2008,42(S):490-494.
[8]ASMEⅢ(2004 edition),Rules for Construction of Nuclear Facility Components[S].
[2]唐永进.压力管道应力分析的内容及特点[J].石油化工设计,2008,25(2):20-24.
[3]陈敏,张周红.复杂管道应力分析中的支吊架布置方法[J].压力容器,2009,26(3):21-25.
[4]赵艳梅,张文格,王冰.压力管道应力分析的一般途径与可靠性讨论[J].压力容器,2001,18(4):61-63.
[5]刘锐,李铁萍,张春明.基于RCC-M与ASME的核2/3级管道应力评定比较[J].压力容器,2013,30(3):52-56.
[6]RCC-M(2002 edition+2002 add),Design and Construction Rules for Mechanical Components of PWR Nuclear Islands[S].
[7]戴守通,汪军,韩治.中国先进研究对主回路出堆管接管载荷优化分析[J].原子能科学技术,2008,42(S):490-494.
[8]ASMEⅢ(2004 edition),Rules for Construction of Nuclear Facility Components[S].