反应堆一回路结构材料与去污液的相容性  

Compatibility of Structure Materials of Primary Loop in Reactor and Decontamination Solution

作　　者：赵宇翔[1] 康武[1] 吴昉赟 文杰 庞鹏 ZHAO Yuxiang;KANG Wu;WU Fangyun;WEN Jie;PANG Peng(Science and Technology on Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu 610213,China;Nuclear Power Operation Management Co.,Ltd.,Haiyan 314300,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]中核核电运行管理有限公司,海盐314300

出　　处：《机械工程材料》2020年第11期15-20,共6页Materials For Mechanical Engineering

摘　　要：在95℃下采用三步化学去污法对5种反应堆一回路结构材料进行浸泡腐蚀试验,研究了结构材料在去污液中的电化学性能以及二者的相容性,并在06Cr18Ni11Ti奥氏体不锈钢上预制氧化膜,对该三步化学去污工艺的效果进行了验证。结果表明:5种材料在去污液中的腐蚀速率均符合要求,0Cr17Ni4Cu4Nb马氏体不锈钢的腐蚀质量损失与腐蚀速率明显高于06Cr18Ni11Ti、06Cr19Ni10N奥氏体不锈钢和00Cr30Ni59Fe10、00Cr25Ni35AlTi镍基合金的;材料的腐蚀主要由草酸柠檬酸盐溶液引起;浸泡试验后,5种试验材料均无点蚀及晶间腐蚀等现象;该三步化学去污工艺对06Cr18Ni11Ti奥氏体不锈钢表面氧化物具有较好的去除效果。Five reactor primary loop structural materials were subjected to immersion corrosion test by threestep chemical decontamination method at 95℃.The electrochemical performance of the materials in the decontamination solution and the compatibility of both were studied,and oxide film was prefabricated on 06Cr18Ni11Ti austenitic stainless steel to verify the effect of the three-step chemical decontamination method.The results show that the corrosion rates of five materials all met the requirements,and the mass loss and corrosion rate of OCr17Ni4Cu4Nb martensitic stainless steel were significantly higher than those of 06Cr18Ni11Ti,06Cr19Ni10N austenitic stainless steels and 00Cr30Ni59Fe10,00Cr25Ni35AlTi nickel based alloys.The material corrosion was mainly caused by oxalic acid citrate solution.There was no pitting corrosion and intergranular corrosion among the five experimental materials after immersion test.The three-step chemical decontamination process had a good removal effect on the surface oxides of 06Cr18Ni11Ti austenitic stainless steel.

关 键 词：一回路 结构材料 去污液 相容性 电化学性能 

分 类 号：TL944[核科学技术—辐射防护及环境保护]