机译:轻水堆条件下奥氏体不锈钢的腐蚀疲劳裂纹扩展行为
Paul Scherrer Institute (PSI), Nuclear Energy and Safety Research Department. Laboratory for Nuclear Materials, 5232 Villigen PSI. Switzerland;
Paul Scherrer Institute (PSI), Nuclear Energy and Safety Research Department. Laboratory for Nuclear Materials, 5232 Villigen PSI. Switzerland;
Paul Scherrer Institute (PSI), Nuclear Energy and Safety Research Department. Laboratory for Nuclear Materials, 5232 Villigen PSI. Switzerland;
A. Stainless steel; C. Corrosion fatigue; C. Reactor conditions;
机译:轻水反应堆条件下奥氏体不锈钢的腐蚀疲劳萌生和短裂纹扩展行为
机译:低合金反应堆压力容器钢在沸水反应堆条件下的腐蚀疲劳裂纹扩展行为
机译:CF8A奥氏体不锈钢在模拟压水堆环境中腐蚀疲劳过程中的组织演变和氧化行为
机译:轻水反应器环境中奥氏体不锈钢的辐照应力腐蚀裂纹扩展速率
机译:氢对亚稳态和稳定奥氏体不锈钢疲劳裂纹扩展过程中组织演变的影响
机译:含亚硝酸盐氯化物溶液中奥氏体不锈钢的应力腐蚀开裂
机译:AISI 310S奥氏体不锈钢不同焊接的应力腐蚀开裂行为,2304双相不锈钢
机译:在211轻水反应堆环境中奥氏体不锈钢的光滑疲劳试样中的裂纹萌生