压力容器2024，Vol.41Issue(6)：8-15,8.DOI:10.3969/j.issn.1001-4837.2024.06.002
核电站常用管道材料J-C本构模型参数识别及验证
Identification and verification of J-C constitutive model parameters for pipeline materials commonly used in nuclear power plants
摘要
Abstract
In order to study the stress flow and deformation of nuclear power plant pipeline under the action of accidental shock load caused by earthquake and other disasters,the quasi-static and dynamic tensile tests were conducted on commonly used pipeline materials in nuclear power plants,namely carbon steel A106(A-106 GR.B),stainless steel 304L(A-312 TP304L),and alloy steel A335(A-335 GR.B)using an electronic universal testing machine for the quasi-static tests,and a high-speed tensile testing machine for the dynamic tests.Based on the test results,and the J-C constitutive model was successfully fitted and established for these three different materials.The impact model of the pipeline was established using Abaqus finite element analysis software,and the simulation results were validated through an impact test conducted on a test bench.The results show that obvious strain rate strengthening effect can be observed in the three materials.The impact resistance of A335 is better,and there is little difference between 304L and A106 in impact resistance.The test results are in good agreement with the simulated results.The parameters fitted in J-C constitutive model have excellent reliability,which can accurately describe the stress flow and deformation behavior of materials under impact load,and have important significance for simulation analysis of the commonly used pipelines in nuclear power plants under the action of impact load.关键词
核电站管道/力学性能/J-C本构模型/冲击载荷Key words
nuclear power plant pipeline/mechanical property/J-C constitutive model/impact load分类
机械制造引用本文复制引用
高宁,徐刚,张亮,陈勇,戴翔,贾文杰,赵弟宏,范霁康..核电站常用管道材料J-C本构模型参数识别及验证[J].压力容器,2024,41(6):8-15,8.基金项目
上海核工程研究设计院有限公司技术产业项目(22FW1087) （22FW1087）
南京理工大学技术服务项目(1234021160758) （1234021160758）
