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4. 5.0 dpa辐照试样经3%应变SSRT实验后晶界处滑移台阶的EBSD分析
Fig.4. EBSD analyses of the surface steps in grain boundary area for the 5.0 dpa irradiated specimens following a strain of 3% by SSRT test in the primary water(a) SEM image of the analyzed area (b) color coded ML map showing residual strain
