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- [21] AN EMPIRICAL-EVALUATION OF A TRANSITION-TEMPERATURE SHIFT IN LIGHT WATER-REACTOR PRESSURE-VESSEL STEELS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 44 : 223 - 224
- [22] LIGHT WATER-REACTOR PRESSURE-VESSEL SURVEILLANCE DOSIMETRY USING SOLID-STATE TRACK RECORDERS NUCLEAR TRACKS AND RADIATION MEASUREMENTS, 1984, 8 (1-4): : 275 - 280
- [23] APPLICATION OF SOLID-STATE TRACK RECORDERS IN LIGHT WATER-REACTOR PRESSURE-VESSEL SURVEILLANCE DOSIMETRY NUCLEAR TRACKS AND RADIATION MEASUREMENTS, 1983, 7 (1-2): : 63 - &
- [24] Effect of Light Water Reactor Water Environments on the Fatigue Life of Reactor Materials JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2017, 139 (06):
- [25] AN EMPIRICAL-APPROACH TO FATIGUE CRACK-GROWTH DATA FOR FERRITIC STEELS IN A PRESSURIZED WATER-REACTOR ENVIRONMENT NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1985, 24 (01): : 53 - 62
- [27] THE INFLUENCE OF ENVIRONMENT AND TEMPERATURE ON THE FATIGUE CRACK-GROWTH BEHAVIOR OF A PRESSURE-VESSEL STEEL RES MECHANICA, 1986, 19 (03): : 227 - 246
- [30] MONITORING OF THERMAL-SHOCK INDUCED CRACK-GROWTH IN A FEED WATER NOZZLE CORNER OF A REACTOR PRESSURE-VESSEL BY ACOUSTIC-EMISSION NDT INTERNATIONAL, 1986, 19 (03): : 197 - 202