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
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

图6. 0.5 dpa辐照试样经3%应变SSRT实验后变形结构的TEM像及分析

Fig.6. TEM images and analyses of deformation structures for the 0.5 dpa irradiated specimens following a strain of 3% by SSRT test in the primary water(a) image of the materials confirming the presence of cleared channels (b, c) accumulation of several stacking faults and dislocations in a channel (d) a channel demonstrated several stages of the evolution process, with the head of the channel marked by several dislocations, followed by planar stacking faults, and finally left behind a channel with reduced defect density (e) grain boundary regions experiencing more signification straining by the interaction of dislocation channels (f) high magnification view of a channel with feeding dislocations to the grain boundary region