国产反应堆压力容器用16MND5钢的蠕变损伤本构模型研究  

Study on the Creep Damage Constitutive Models of 16MND5 Steel for Domestic Reactor Pressure Vessel

作　　者：苏东川[1] 张瀛[1] 杜娟[1] 孙英学[1] 傅孝龙[1] 李辉 邵雪娇[1] 郭素娟 Su Dongchuan;Zhang Ying;Du Juan;Sun Yingxue;Fu Xiaolong;Li Hui;Shao Xuejiao;Guo Sujuan(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;Division of Process Equipment Science&Engineering Physics,East China University of Science and Technology,Shanghai,200237,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213 [2]华东理工大学过程设备科学与工程研究室,上海200237

出　　处：《核动力工程》2022年第1期232-237,共6页Nuclear Power Engineering

摘　　要：为了获得反应堆压力容器(RPV)材料在高温下的蠕变行为,保证RPV在严重事故工况下的完整性,本研究对国产RPV用16MND5钢的高温蠕变性能进行了测试,获得了600~900℃下材料的蠕变性能,并基于应变强化的基本蠕变本构模型与基于延性耗竭理论的蠕变损伤模型,建立了适用于16MND5钢的蠕变损伤本构模型,给出了材料的蠕变损伤模型参数。结果表明,本文提出的蠕变损伤本构模型的有限元模拟数据与试验数据符合性较好,验证了此蠕变损伤模型的正确性。该方法可用于严重事故情况下RPV的蠕变损伤分析,为RPV的完整性分析提供支持。In order to obtain the creep behavior of reactor pressure vessel(RPV) materials at high temperature and ensure the integrity of RPV under severe accident conditions, the high temperature creep properties of 16 MND5 steel for domestic RPV were tested, and the creep property of the material at 600~900℃ was obtained. Based on the basic creep constitutive model of strain strengthening and the creep damage model based on ductile depletion theory, a creep damage constitutive model suitable for 16 MND5 material is established, and the creep damage model parameters are given. Results show that the finite element simulation data of the creep damage constitutive model proposed in this paper are in good agreement with the experimental data, which verifies the correctness of the creep damage model. This method can be used for the creep damage analysis of RPV under serious accidents, and provide support for the integrity analysis of RPV.

关 键 词：反应堆压力容器(RPV) 完整性分析 高温蠕变 蠕变损伤本构模型 

分 类 号：TL34[核科学技术—核技术及应用]