共 50 条
- [1] Fatigue crack growth curve for austenitic stainless steels in BWR environment JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2001, 123 (02): : 166 - 172
- [2] Crack Growth Rates of Irradiated Commercial Stainless Steels in BWR and PWR Environments 15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 2011, : 1229 - 1240
- [3] Crack growth rates of irradiated austenitic stainless steels in BWR environments at 289°c PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2007, VOL 1: CODES AND STANDARDS, 2007, 1 : 253 - 268
- [4] THE EFFECT OF COLD WORK ON MICROSTRUCTURE AND SCC SUSCEPTIBILITY IN SIMULATED BWR ENVIRONMENT FOR NON-SENSITIZED AUSTENITIC STAINLESS STEELS 15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 2011, : 425 - 437
- [5] RE-EVALUATION OF FATIGUE CRACK GROWTH CURVE FOR AUSTENITIC STAINLESS STEELS IN BWR ENVIRONMENT PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, PVP 2012, VOL 1, 2012, : 631 - 636
- [6] Evaluation of Crack Growth Rates and Microstructures Near the Crack Tip of Neutron-Irradiated Austenitic Stainless Steels in Simulated BWR Environment PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018, : 1039 - 1054
- [7] Effect of Chloride Transients on Crack Growth Rates in Low Alloy Steels in BWR Environments PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018, : 433 - 445
- [9] Characteristics of crack propagation through SCC under BWR conditions in stainless steels stabilized with titanium or niobium PROCEEDINGS OF THE NINTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 1999, : 299 - 308
- [10] Effect of Long-Term Thermal Aging on SCC Initiation Susceptibility in Low Carbon Austenitic Stainless Steels PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018, : 663 - 672