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7. 核用304不锈钢3%应变SSRT实验后SCC行为的表面SEM像及滑移台阶与晶界作用示意图
Fig.7. SEM images of stress corrosion cracking at surfaces of nuclear grade 304 stainless steel following a strain of 3% by the SSRT tests (a~d) and corresponding schematics showing the interaction between slip step and grain boundary crack (e~h)(a, e) solution annealed (b, f) 0.5 dpa (c, g) 1.5 dpa (d, h) 5.0 dpa
