表面状态对核电关键材料腐蚀和应力腐蚀的影响
韩恩厚, 王俭秋

Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials
HAN En-Hou, WANG Jianqiu
图7 核级304不锈钢无应变与3%应变样品的沿晶氧化与辐照剂量的关系;辐照促进应力腐蚀开裂的敏感性(裂纹数量与长度)与辐照剂量的关系[46]
Fig.7 Depth of intergranular oxide in strain-free and 3% strained specimens as a function of irradiation dose (PWR—pressurized water reactor, DH—dissolved hydrogen) (a), irradiation-assisted stress corrosion cracking (IASCC) susceptibility as measured by crack number and crack length per unit area as a function of irradiation dose (b)[46]