汽轮机膨胀节塑性变形损伤后结构力学性能分析  

Mechanical Analysis of Steam Turbine Bellows after Plastic Deformation Damage

作　　者：王俊[1] 原帅 徐应军[3] 贾凯利 黄祥君 刘思伟 陈明亚[1] 余伟炜[1] 唐敏锦 贾文清 Wang Jun;Yuan Shuai;Xu Yingjun;Jia Kaili;Huang Xiangjun;Liu Siwei;Chen Mingya;Yu Weiwei;Tang Minjin;Jia Wenqing(Suzhou Nuclear Power Research Institute,Suzhou 215004,China;China General Nuclear Power Operation Co.,Ltd.,Shenzhen 518000,China;Daya Bay Nuclear Power Operation Management Co.,Ltd.,Shenzhen 518000,China)

机构地区：[1]苏州热工研究院有限公司,江苏苏州215004 [2]中广核核电运营有限公司,广东深圳518000 [3]大亚湾核电运营管理有限责任公司,广东深圳518000

出　　处：《压力容器》2020年第2期64-70,共7页Pressure Vessel Technology

基　　金：国防科技重点实验室稳定支持项目(HTKJ2019KL011004);国家自然科学基金项目(51275338,51435012);江苏省自然科学基金项目(BK20171223)。

摘　　要：汽轮机金属膨胀节在制造、安装和运行阶段常发生塑性变形,影响其服役工况下达到设计膨胀补偿量和安全运行性能的要求。目前,核电厂关键设备主要设计参考规范(RCC-M、ASME规范第Ⅲ和ⅩⅢ卷等)正逐步发展为基于弹塑性理论的分析方法。针对某核电厂汽轮机膨胀节发生的塑性变形损伤,基于ASME规范和有限元软件ANSYS进行了膨胀节塑性变形损伤后结构力学性能分析,包含基于材料真实应力-应变数据的不同工况组合下塑性损伤分析及结构塑性损伤后疲劳寿命的校核。During the manufacture,installation and operation process,plastic deformation damage often occurs in metal bellows expansion joints used in steam turbines,which will affect the expansion compensation and safe operation performance of the bellows.At present,the design codes for nuclear key equipment,such as RCC-M,ASME Code VolumeⅢandⅩⅢ,are gradually developing into the analysis method based on elastic-plastic theory.In this paper,mechanical analysis of the bellows expansion joint used in a nuclear power plant after plastic deformation damage was analyzed based on ASME code and using finite element software ANSYS,including plastic damage analysis under combination of different working conditions based on material real stress-strain data and fatigue life assessment after plastic damage.

关 键 词：汽轮机 膨胀节 塑性损伤 疲劳 应力三轴度 有限元 

分 类 号：TH131.9[机械工程—机械制造及自动化] TK26[动力工程及工程热物理—动力机械及工程]