核安全一级高温管道系统结构分析与安全评估方法研究
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摘要
为解决复杂核安全一级高温管道系统结构分析与评定工程问题,在管道分析软件与核级高温评定规范ASME-NH之间建立了一座桥梁。首先,对管道结构(直管及弯管)在不同载荷作用下的应力状态解析解进行了详细推导分析,并且与有限元数值解进行了误差分析。结果显示,给出的直管及弯管结构应力状态解析解具有很好的准确性。随后,将一维管线力学分析模型与截面三维应力状态解析解相结合,给出了高温管道系统结构分析、评定方法及应用步骤,将ASME-NH-3650规范内容明确化。
To solve the problems encountered in the design of the piping system at elevated temperature, the present paper demonstrates a methodology of structural analysis and safety evaluation procedures for high temperature piping. A bridge between piping analysis software and ASME-NH is established. Firstly, the detailed analytical solutions of stress components for piping components(straight pipe and bent pipe or elbow) under multiple loading combinations are proposed. Then, the analytical predictions of the stresses are compared with the solutions given by finite element analysis(FEA). The results show that the proposed analytical results agree with FEA results very well. And finally, the piping structural analysis and integrity assessment procedures are given by coupling the pipe line model and the newly proposed analytical solutions. And thus a method to implement the piping design criteria of ASME-NH-3600 for the analysis of nuclear class 1 piping components is provided.
To solve the problems encountered in the design of the piping system at elevated temperature, the present paper demonstrates a methodology of structural analysis and safety evaluation procedures for high temperature piping. A bridge between piping analysis software and ASME-NH is established. Firstly, the detailed analytical solutions of stress components for piping components(straight pipe and bent pipe or elbow) under multiple loading combinations are proposed. Then, the analytical predictions of the stresses are compared with the solutions given by finite element analysis(FEA). The results show that the proposed analytical results agree with FEA results very well. And finally, the piping structural analysis and integrity assessment procedures are given by coupling the pipe line model and the newly proposed analytical solutions. And thus a method to implement the piping design criteria of ASME-NH-3600 for the analysis of nuclear class 1 piping components is provided.
引文
[1]龚玮,张小春,王晓,等.钍基熔盐堆TMSR回路管道系统应力分析与评定[J].核动力工程,2015,36(5):152-155.
[2]ASME.Rules for construction of nuclear facility components,division 5 high temperature reactors[S].New York:ASME Boiler and Pressure Vessel Committee on Construction of Nuclear Facility Components,2017:163-188.
[3]ASME.Rules for construction of nuclear facility compnents,division 1,subsection nh class 1 compoments in elevated temperature service[S].New York:ASMEBoiler and Pressure Vessel Committee on Nuclear Power,2015:37.
[4]ASME.Rules for construction of nuclear facility components,division 1 subsection nb class 1components[S].New York:ASME Boiler and Pressure Vessel Committee on Nuclear Power,2015:112-114.
[2]ASME.Rules for construction of nuclear facility components,division 5 high temperature reactors[S].New York:ASME Boiler and Pressure Vessel Committee on Construction of Nuclear Facility Components,2017:163-188.
[3]ASME.Rules for construction of nuclear facility compnents,division 1,subsection nh class 1 compoments in elevated temperature service[S].New York:ASMEBoiler and Pressure Vessel Committee on Nuclear Power,2015:37.
[4]ASME.Rules for construction of nuclear facility components,division 1 subsection nb class 1components[S].New York:ASME Boiler and Pressure Vessel Committee on Nuclear Power,2015:112-114.