夹杂物对压水堆核电站用Z2CN19-10不锈钢应力腐蚀开裂的影响  

Effect of Inclusions on Stress Corrosion Cracking of Z2CN19-10 Stainless Steel Used for Pressurized-Water Reactor Power Plant

作　　者：马新朝 刘璐[2] 洪源平 李世伟 步伟东 

机构地区：[1]中国核电工程有限公司,北京100086 [2]苏州热工研究院有限公司,苏州215004 [3]中核核电运行管理有限公司,海盐314300 [4]秦山核电有限公司,海盐314300

出　　处：《机械工程材料》2016年第3期10-14,共5页Materials For Mechanical Engineering

基　　金：国家科技重大专项资助项目(2011ZX06004-002)

摘　　要：在模拟压水堆正常工况环境中对正常组织和夹杂物超标的Z2CN19-10不锈钢U型弯曲试样进行恒应力浸泡试验,并分别在250mV外加电位下、在富含溶解氧和氯离子溶液中以及在沸腾MgCl_2溶液中进行加速应力腐蚀试验,研究了夹杂物对该钢应力腐蚀开裂的影响。结果表明:在模拟压水堆正常工况环境以及250mV外加电位、富含溶解氧和氯离子的溶液中,超标的夹杂物均不会导致试验钢出现应力腐蚀开裂;在沸腾MgCl_2溶液中,两种试样均发生了应力腐蚀开裂,但在裂纹萌生区和扩展区未发现夹杂物,说明应力腐蚀开裂与夹杂物无明显关系。Immersion test at constant stress was carried out on U-shaped bending stainless steel specimen with normal microstructure and excessive inclusions in the normal environment of simulated pressurized-water reactor（PWR）,as well as accelerated stress corrosion tests at 250 mV applied potential,in the solution rich in dissolved oxygen and chlorine ion,and in boiling MgCl2 solution.The effect of inclusions on the stress corrosion cracking of the steel was studied.The results show that,in the environment of simulated PWR,and in the 250 mV applied potential and the solution rich in dissolved oxygen and chlorine ion,excessive inclusions did not result in stress corrosion cracking.In boiling MgCl2 solution,stress corrosion cracking was found in the two kinds of specimens,but no inclusions were found in the crack initiation and propagation regions,there was no evident relationship between inclusions and stress corrosion cracking.

关 键 词：压水堆 夹杂物 Z2CN19-10不锈钢 应力腐蚀开裂 

分 类 号：TG113.23[金属学及工艺—物理冶金]