核用304不锈钢辐照促进应力腐蚀开裂研究
邓平1,2,孙晨3,彭群家1,4(
),韩恩厚1,柯伟1,焦治杰5
),韩恩厚1,柯伟1,焦治杰5
Study on Irradiation Assisted Stress Corrosion Cracking of Nuclear Grade 304 Stainless Steel
Ping DENG1,2,Chen SUN3,Qunjia PENG1,4(),En-Hou HAN1,Wei KE1,Zhijie JIAO5
),En-Hou HAN1,Wei KE1,Zhijie JIAO5
图8. 核用304不锈钢间断SSRT实验后表面SCC裂纹统计结果
Fig.8. Summary of SCC cracks on surfaces of nuclear grade 304 stainless steel following interrupted SSRT test in the primary water
