超临界水冷堆候选包壳管材的低周疲劳性能试验研究  

Experimental Study on Low-Cycle Fatigue Properties of Supercritical Water-cooled Reactor Candidate Cladding Material

作　　者：赵宇翔[1,2] 熊茹 梁波[1] 唐睿[1] Zhao Yuxiang;Xiong Ru;Liang Bo;Tang Rui(Science and Technology on Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;Polymer Research Institute,Sichuan University,Chengdu,610065,China)

机构地区：[1]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 [2]四川大学高分子研究所,成都610065

出　　处：《核动力工程》2023年第5期237-243,共7页Nuclear Power Engineering

基　　金：国家重点研发计划(2018YFE0116200)。

摘　　要：为了获得超临界水冷堆(SCWR)候选包壳材料20Cr-25Ni的低周疲劳性能数据,为SCWR的设计、研发和工程提供技术参考,本文采用MTS809试验机开展了20Cr-25Ni在室温、500℃、650℃、800℃空气环境中的低周疲劳试验,获得了多级循环滞回曲线、循环应力-应变曲线、应力幅与循环分数关系曲线以及循环应力应变模型和低周疲劳Manson-Coffin模型参数。20Cr-25Ni的低周疲劳试验结果表明:随着温度的升高,20Cr-25Ni不锈钢管材的抗疲劳性能不断下降,在500℃、650℃显示出较明显的循环硬化。因此,在650℃以下该包壳材料具有较好抗疲劳性能,当SCWR堆芯最高温度的设计高于650℃后,使用该材料作为包壳材料需要谨慎。In order to obtain the low cycle fatigue performance data of 20Cr-25Ni,a candidate cladding material for supercritical water cooled reactor(SCWR),and to provide technical reference for the design,development and engineering of SCWR,the low cycle fatigue tests of 20Cr-25Ni at room temperature,500℃,650℃ and 800℃ were carried out on MTS809 testing machine,and the multi-level cyclic hysteresis curve,cyclic stress-strain curve,the relationship curve between stress amplitude and cyclic fraction,cyclic stress-strain model and low cycle fatigue Manson-Coffin model parameters were obtained.The results of low cycle fatigue test of 20Cr-25Ni show that the fatigue resistance of 20Cr-25Ni stainless steel pipe decreases with the increase of temperature,and shows obvious cyclic hardening at 500℃ and 650℃.Therefore,the cladding material has good fatigue resistance below 650℃.When the maximum core temperature of SCWR is higher than650℃,it is necessary to be careful to use this material as cladding material.

关 键 词：超临界水冷堆(SCWR) 包壳管 不锈钢 低周疲劳 曲线 

分 类 号：TL341[核科学技术—核技术及应用]