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中国核电工程有限公司
纸质出版日期:2013
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[1]宁庆坤,田金梅.二代改进型核电站管道系统应力分析与评定[J].核技术,2013,36(04):62-66.
NING Qingkun TIAN Jinmei. Stress analysis and evaluation of improved second-generation nuclear power plant piping systems[J]. Nuclear techniques, 2013, 36(4): 040612
[1]宁庆坤,田金梅.二代改进型核电站管道系统应力分析与评定[J].核技术,2013,36(04):62-66. DOI: 10.11889/j.0253-3219.2013.hjs.36.040612.
NING Qingkun TIAN Jinmei. Stress analysis and evaluation of improved second-generation nuclear power plant piping systems[J]. Nuclear techniques, 2013, 36(4): 040612 DOI: 10.11889/j.0253-3219.2013.hjs.36.040612.
管道是核电站中的重要部件。为了使管道满足规范要求
需要对管道进行应力分析与评定。本文分析了二代改进型核电站1级和2级管道应力分析与评定过程
论述了不同载荷下管道应力的计算方法
并分析了RCC-M规范版本的变化对管道应力分析结果的影响。最后
以岭澳核电站二期工程安全注入系统为例
对管道进行了应力分析与评定
满足了RCC-M规范的设计要求
并输出了支撑载荷、接管载荷、管道位移等接口参数。本文可以为二代改进型核电站管道系统应力分析与评定提供帮助。
Background: Piping is an important part in nuclear power plants.Purpose: In order to make piping meet the specification requirements
it is necessary to analyze and evaluate piping stress.Methods: This paper deals with the stress analysis and evaluation of the class 1 and class 2 piping of improved second-generation nuclear power plants
and discusses the calculation methods of piping stress due to various loads.Also
the effects of changing the RCC-M code edition on the calculation of piping stress are summarized.Results: Taking the LingAo Nuclear Power Plant Phase II engineering safety injection system as an example
the piping stress analysis and evaluation are performed
and the results meet the RCC-M code requirements.Besides
the interface parameters including the support loads
nozzle loads
displacements of the piping and so on are obtained.Conclusions: This paper will provide technical support for stress analysis and evaluation of improved second-generation nuclear power plant piping systems.
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