辐照监督重组冲击试样插入段选材的力学与数值模拟分析  

Mechanical and Numerical Simulation Analysis for Insertion Section of Irradiation Surveillance Reconstitution Charpy Specimen

作　　者：唐云鹏 朱卉平 佟振峰 马雁[1] 郝祖龙 王栋 Tang Yunpeng;Zhu Huiping;Tong Zhenfeng;Ma Yan;Hao Zulong;Wang Dong(School of Nuclear Science and Engineering,North China Electric Power University,Beijing,102206,China;Science and Technology on Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]华北电力大学核科学与工程学院,北京102206 [2]中国核动力研究设计院反应堆燃料及材料重点实验室,成都610213

出　　处：《核动力工程》2023年第S01期113-118,共6页Nuclear Power Engineering

基　　金：国家重点研发计划(2020YFB1901501);国家自然科学基金(12027813);中央高校基本科研业务费(2020MS031)。

摘　　要：为解决核反应堆堆内空间有限而导致的辐照监督试样短缺问题,采用试样重组技术可利用有限的夏比冲击试样获得更多冲击数据,为核电厂的延寿提供数据支撑。本研究采用反应堆压力容器材料Ni-CrMo-V钢,分别在母材、焊缝和热影响区位置选材制备夏比冲击试样。结果表明,冲击试样在上平台区产生最大的塑性变形,而热影响区选材的上平台断头具有最大的塑性变形区,其长度约为8.5 mm。因此,Ni-CrMo-V钢重组试样的插入段最大长度应不大于19 mm。采用GTN模型模拟冲击过程与试验结果偏差小于5%,可有效用于冲击试样变形区长度的模拟。To address the shortage of irradiation surveillance specimens due to limited space in nuclear reactors,limited Charpy specimen can be used to gather more impact data by specimen reconstitution techniques,so as to support the life extension of the nuclear power plant.In this study,Ni-Cr-Mo-V steel,which is used in reactor pressure vessels,was selected to create Charpy impact specimens from the base material,welds,and hot zones.The results showed that the Charpy specimen had the largest plastic deformation in the upper shelf,while the upper shelf fracture selected in the heat affected zone had the largest plastic deformation area with a length about 8.5 mm.Therefore,the maximum insertion length of the reconstituted Ni-Cr-Mo-V steel specimen should not exceed 19mm.The GTN model simulation of the impact process deviated from the test results by less than 5%,making it effective for simulating the deformation length of the impact specimen.

关 键 词：辐照监督 试样重组 插入段 硬度 GTN模型 

分 类 号：TL341[核科学技术—核技术及应用]