共 50 条
- [1] FURTHER DEVELOPMENT OF A MODEL FOR PREDICTING CORROSION FATIGUE CRACK-GROWTH IN REACTOR PRESSURE-VESSEL STEELS [J]. JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 1987, 109 (03): : 340 - 346
- [2] FATIGUE CRACK-GROWTH OF IRRADIATED PRESSURE-VESSEL STEELS IN SIMULATED, REACTOR-GRADE WATER ENVIRONMENT [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 34 (JUN): : 182 - 183
- [5] CYCLIC CRACK-GROWTH BEHAVIOR OF REACTOR PRESSURE-VESSEL STEELS IN LIGHT WATER-REACTOR ENVIRONMENTS [J]. JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 1986, 108 (01): : 26 - 30
- [8] ON THE ROLE OF PRIOR HYDROGEN ATTACK DAMAGE IN INFLUENCING FATIGUE CRACK-GROWTH IN PRESSURE-VESSEL STEELS [J]. JOURNAL OF METALS, 1983, 35 (12): : 28 - 28
- [9] VISUAL OBSERVATION OF FATIGUE CRACK-GROWTH BEHAVIOR OF REACTOR PRESSURE-VESSEL STEEL IN HIGH-TEMPERATURE PRESSURIZED WATER [J]. TETSU TO HAGANE-JOURNAL OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1984, 70 (13): : 1229 - 1229