共 50 条
- [44] DEVELOPMENT OF LEAK BEFORE BREAK ASSESSMENT GUIDELINES FOR SODIUM COOLED FAST REACTORS IN JAPAN PROCEEDINGS OF ASME 2021 PRESSURE VESSELS AND PIPING CONFERENCE (PVP2021), VOL 1, 2021,
- [45] LEAK-BEFORE-BREAK ASSESSMENT OF A CRACKED REACTOR VESSEL NOZZLE USING 3D CRACK MESHES PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2016, VOL 6A, 2017,
- [46] A NOVEL APPROACH FOR THE STRUCTURAL INTEGRITY ASSESSMENT OF CANDU REACTOR PRESSURE TUBES UPB Scientific Bulletin, Series B: Chemistry and Materials Science, 2023, 85 (04): : 211 - 222
- [47] A NOVEL APPROACH FOR THE STRUCTURAL INTEGRITY ASSESSMENT OF CANDU REACTOR PRESSURE TUBES UNIVERSITY POLITEHNICA OF BUCHAREST SCIENTIFIC BULLETIN SERIES B-CHEMISTRY AND MATERIALS SCIENCE, 2023, 85 (04): : 211 - 222
- [48] DEVELOPMENT OF INITIAL INPUT PARAMETERS FOR A PROBABILISTIC PIPE RUPTURE ASSESSMENT CODE FOR NUCLEAR REACTOR COOLANT PRESSURE BOUNDARY LEAK-BEFORE-BREAK ANALYSES PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2010, VOL 6, PTS A AND B, 2010, : 641 - 647