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作 者:陈明亚[1] 余伟炜[1] 薛飞[1] 高红波 孙兴悦 石守稳[2] 陈旭[2] 师金华 Chen Mingya;Yu Weiwei;Xue Fei;Gao Hongbo;Sun Xingyue;Shi Shouwen;Chen Xu;Shi Jinhua(Suzhou Nuclear Power Research Institute,Suzhou 215000,China;Tianjin University,Tianjin 300072,China)
机构地区:[1]苏州热工研究院有限公司,江苏苏州215000 [2]天津大学,天津300072
出 处:《压力容器》2019年第10期16-21,共6页Pressure Vessel Technology
基 金:国家自然科学基金项目(51275338,51435012);国防科技重点实验室稳定支持项目(HTKJ2019KL011004);江苏省自然科学基金项目(BK20171223,BK20150280)
摘 要:对管道热冲击应力快速计算方法和核一级设备设计规范(对比RCC-M规范和ASME规范)中管道壁厚径向线性温度分布引起应力分类方法展开研究,探讨了核电厂在线疲劳监测系统中快速、精确计算管道热疲劳应力的方法。以核电厂某典型的管道T型接头为分析对象,分析了基于格林函数快速计算管道热冲击应力响应方法的有效性。研究结果表明,参考瞬态下,格林函数计算结果与有限元数值仿真结果偏差在0.5%范围之内,基于格林函数快速计算管道热冲击应力具有较高的可靠性;参考分析瞬态下径向线性温度分布引起管道轴向最大应力值占设计规范限制3Sm的7.03%,相比ASME规范的设计要求,RCC-M规范的分析准则存在不必要的保守性。The stress classification method caused by the radial linear temperature distribution along the wall thickness of the pipe was studied based on the method of rapid calculations of the thermal shock stress of the pipe and according to the nuclear grade design code(such as the RCC-M and ASME codes),and a fast and accurate method for calculating the thermal fatigue stress in the online fatigue monitoring system of a nuclear power plant was discussed in this paper.By taking the typical pipeline T-joint of a nuclear power plant as the analysis object,the effectiveness of the rapid calculation method of the thermal shock stress based on the Green′s function was analyzed.The research results show that the error between the results of the Green′s function and the numerical simulation results of the finite element analysis was within 0.5%.The rapid calculation method of the thermal shock stress based on the Green′s function has higher reliability.The maximum axial stress of the pipe caused by the radial linear temperature distribution under the reference transient accounts for 7.03%of the design code limit 3Sm.Compared to the design requirements in the ASME code,the analysis criteria in the RCC-M code are unnecessarily conservative.
分 类 号:TH49[机械工程—机械制造及自动化] TQ055.8[化学工程]
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