共 50 条
- [21] Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels EFFECTS OF RADIATION ON MATERIALS: 23RD INTERNATIONAL SYMPOSIUM, 2008, 1492 : 83 - 94
- [22] THE ROLE OF GRAIN SIZE IN PREDICTING CLEAVAGE FRACTURE TOUGHNESS OF PRESSURE VESSEL STEELS PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 6B: MATERIALS AND FABRICATION, 2014,
- [23] REFERENCE FRACTURE-TOUGHNESS CURVES FOR IRRADIATED PRESSURE-VESSEL STEELS JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 1980, 102 (01): : 101 - 108
- [24] Fracture toughness evaluation using small specimens for reactor pressure vessel steels 2000, American Society of Mechanical Engineers (413):
- [25] Fracture toughness of highly irradiated pressure vessel steels in the upper shelf temperature ASME Pressure Vessels Piping Div. Publ. PVP,
- [26] Analysis of warm prestressing effect on fracture toughness of reactor pressure vessel steels Strength of Materials, 2010, 42 : 120 - 123
- [29] LOCAL APPROACH TO FRACTURE APPLICATION TO PREDICT IRRADIATION EFFECT ON FRACTURE TOUGHNESS OF PRESSURE VESSEL STEELS PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2005, (03): : 24 - +
- [30] Micromechanical modeling of ductile fracture initiation to predict fracture toughness of reactor pressure vessel steels JOURNAL DE PHYSIQUE IV, 1996, 6 (C6): : 53 - 64