共 50 条
- [1] Effects of Boiling Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2016, 138 (03):
- [3] A FATIGUE CRACK GROWTH MODEL FOR TYPE 304 AUSTENITIC STAINLESS STEELS IN A PRESSURIZED WATER REACTOR ENVIRONMENT PROCEEDINGS OF ASME 2021 PRESSURE VESSELS AND PIPING CONFERENCE (PVP2021), VOL 1, 2021,
- [5] Fatigue Life of the Strain Hardened Austenitic Stainless Steel in Simulated Pressurized Water Reactor Primary Water JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2014, 136 (03):
- [6] TEMPERATURE DEPENDENCE OF REACTOR WATER ENVIRONMENTAL FATIGUE EFFECTS ON CARBON, LOW ALLOY AND AUSTENITIC STAINLESS STEELS PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 1, 2009, : 201 - 211
- [7] FATIGUE STRAIN-LIFE BEHAVIOR OF AU.STENITIC STAINLESS STEELS IN PRESSURIZED WATER REACTOR ENVIRONMENTS ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2015, VOL 1A, 2015,
- [8] Microstructural effects in austenitic stainless steel materials irradiated in a pressurized water reactor PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2, 1997, : 725 - 733
- [9] Influence of Mean Strain on Fatigue Life of Stainless Steel in Pressurized Water Reactor Water Environment JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2021, 143 (04):