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2. 0.5 dpa辐照试样经3%应变SSRT实验后应力腐蚀开裂(SCC)区域的EBSD分析
Fig.2. EBSD analyses of stress corrosion cracking (SCC) area for the 0.5 dpa irradiated specimens following a strain of 3% by slow strain rate tensile (SSRT) test in the primary water (The cracked grain boundaries are highlighted by black arrows, LAB—low-angle grain boundary, RGB—random grain boundary, CSL—coincidence site lattice special boundary)(a) SEM image of the analyzed area (b) color coded local misorientation (ML) map showing residual strain (c) distribution of local misorientations (d) crystal orientation (e) grain boundary character (f) Schmidt factor
