摘要
研究了核反应堆弹簧材料用0Cr20Ni55Mo3Nb5Ti(Inconel-718)镍基合金材料时效强化状态下在150~650℃范围内的高温弹塑性特征,并采用多种函数模型对其高温应力-应变实测数据进行了本构关系拟合计算和对比。结果表明:经过970℃×1 h,空冷+720℃×8 h,炉冷+620℃×8 h,空冷的三步法时效强化处理后,Inconel-718合金兼具较高的R_(p0.01)值和室温伸长率。Boltzmann函数模型对时效强化Inconel-718合金材料在1.5%应变范围内的高温σ-ε实测数据具有良好的拟合效果和预测计算精度,适用于核反应堆弹簧材料的选材和结构设计。
High-temperature elastic-plastic characteristics from 150℃to 650℃of aging strengthened 0Cr20Ni55Mo3Nb5Ti(Inconel-718)nickel-based alloy used for nuclear reactor spring were researched,and various functional models were used to fitting calculation and comparison of the constitutive relations based on the measured stress-strain data at high temperature.The results show that higher R_(p0.01)value and room temperature elongation of the Inconel-718 alloy are obtained after 3-steps heat treatment of 970℃×1 h,air cooling+720℃×8 h,furnace cooling+620℃×8 h,air cooling.It is found that Boltzmann model has good fitting effect and prediction calculation precision for high-temperatureσ-εconstitutive relations of the aging strengthened Inconel-718 alloy,so that it is also appropriate for the structure design and material selection for nuclear reactors.
作者
屈华鹏
王留兵
王东辉
吴冰洁
冯翰秋
许斌
宋丹戎
郎宇平
Qu Huapeng;Wang Liubing;Wang Donghui;Wu Bingjie;Feng Hanqiu;Xu Bin;Song Danrong;Lang Yuping(Institute of Special Steel,Central Iron and Steel Research Institute,Beijing 100081,China;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu Sichuan 610200,China)
出处
《金属热处理》
CSCD
北大核心
2021年第8期1-7,共7页
Heat Treatment of Metals
基金
国家重点研发计划(2016YFB0300202)。
