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- [1] THE EFFECT OF A LOW CONSTRAINT GEOMETRY ON MEASURED To VALUES FOR A NUCLEAR REACTOR PRESSURE VESSEL FERRITIC STEEL PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 5, 2019,
- [2] FRACTURE TOUGHNESS EVALUATION OF NEUTRON-IRRADIATED REACTOR PRESSURE VESSEL STEEL USING MINIATURE-C(T) SPECIMENS PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2017, VOL 1A, 2017,
- [3] Constraint Effect on Fracture Behavior of Underclad Crack in Reactor Pressure Vessel JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2022, 144 (01):
- [4] CONSTRAINT EFFECT ON FRACTURE MECHANICS EVALUATION FOR AN UNDER-CLAD CRACK IN A REACTOR PRESSURE VESSEL STEEL PROCEEDINGS OF THE ASME 2020 PRESSURE VESSELS & PIPING CONFERENCE (PVP2020), VOL 1, 2020,
- [6] APPLICABILITY OF MINIATURE C(T) SPECIMEN TO EVALUATION OF FRACTURE TOUGHNESS FOR REACTOR PRESSURE VESSEL STEEL PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 6B: MATERIALS AND FABRICATION, 2014,
- [7] Effect of hydrogenation on the fracture mode of a reactor pressure-vessel steel Materials Science, 2009, 45 : 613 - 625
- [10] APPLICABILITY OF MINIATURE C(T) SPECIMEN TO FRACTURE TOUGHNESS EVALUATION FOR THE IRRADIATED JAPANESE REACTOR PRESSURE VESSEL STEEL PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2017, VOL 1A, 2017,