反应堆压力容器用低合金钢回火焊道工艺试验研究

反应堆压力容器用低合金钢回火焊道工艺试验研究 Research on temper bead welding procedure test of the low alloy steel for reactor pressure vessel 金亮 JIN Liang 1 2 first-author 匡艳军 KUANG Yanjun 2 黄腾飞 HUANG Tengfei 2 孙广 SUN Guang 2 邱振生 QIU Zhensheng 2 陈亮 CHEN Liang 2 核电安全监控技术与装备国家重点实验室 核电安全监控技术与装备国家重点实验室 State Key Laboratory of Nuclear Power Safety Monitoring technology and Equipment State Key Laboratory of Nuclear Power Safety Monitoring technology and Equipment 深圳中广核工程设计有限公司 深圳中广核工程设计有限公司 China Nuclear Power Design Co.,Ltd. China Nuclear Power Design Co.,Ltd. 为解决核电厂关键设备在役期间焊接返修后无法实施传统焊后热处理的难题,采用机械-钨极惰性气体保护焊分别在室温和150℃预热条件下对反应堆压力容器用低合金钢进行回火焊道焊接工艺试验,然后测试焊接热影响区的显微硬度、显微组织及冲击韧性。试验结果表明:通过合理控制前三层的焊接热输入,可有效降低焊接热影响区的硬度,并获得综合性能较好的回火索氏体组织,室温条件下的回火焊道焊接热影响区在0℃和-20℃的冲击吸收能量均高于设计要求值。 The conventional postweld heat treatment（PWHT） can not be applied to the key equipment of nuclear power plant after repair welding during service. In order to solve this problem,a mechanized gas tungsten arc welding（GTAW） is used for temper bead welding procedure test of the low alloy steel for reactor pressure vessel under the preheating conditions at room temperature and 150 ℃ respectively,and then the microhardness,microstructure and impact toughness of the heat affected zone（ HAZ） are tested. The results show that the microhardness can be effectively reduced by properly controlling the heat input ratios of the first three layers,and the tempered sorbite structure with good comprehensive properties can be obtained in the HAZ. Both the impact absorption energies at 0 ℃ and 20 ℃ of the HAZ of the temper bead under the preheating conditions at room temperature are higher than the design requirements. 反应堆压力容器 回火焊道 热影响区 微观组织 reactor pressure vessel temper bead heat affected zone microstructure TG44;TM623 国家重点研究发展计划项目(2017YFB0305303) 2022-03-08 6 50