共 27 条
- [3] REACTOR SURVEILLANCE TEST AND FRACTURE-MECHANICS EVALUATION OF IRRADIATION EMBRITTLEMENT IN REACTOR PRESSURE-VESSEL STEELS [J]. JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 1980, 102 (04): : 317 - 326
- [5] STUDY ON LIFE EXTENSION OF AGED RPV MATERIAL BASED ON PROBABILISTIC FRACTURE-MECHANICS - JAPANESE ROUND-ROBIN [J]. JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 1995, 117 (01): : 7 - 13
- [6] EVALUATION OF RADIATION-DAMAGE IN REACTOR PRESSURE-VESSEL STEEL BY ELASTIC-PLASTIC FRACTURE-MECHANICS [J]. JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 1981, 103 (04): : 276 - 281
- [7] Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel [J]. JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2021, 143 (04):
- [8] EXTENSION OF PASCAL4 CODE FOR PROBABILISTIC FRACTURE MECHANICS ANALYSIS OF REACTOR PRESSURE VESSEL IN BOILING WATER REACTOR [J]. PROCEEDINGS OF THE ASME 2020 PRESSURE VESSELS & PIPING CONFERENCE (PVP2020), VOL 1, 2020,
- [10] FRACTURE-MECHANICS DATA DEDUCED FROM THERMAL-SHOCK AND RELATED EXPERIMENTS WITH LWR PRESSURE-VESSEL MATERIAL [J]. JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 1983, 105 (02): : 102 - 110