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- [25] PROBABILISTIC FRACTURE MECHANICS ANALYSIS FOR DEGRADED REACTOR PRESSURE VESSEL IN PRESSURIZED WATER REACTOR NUCLEAR POWER PLANT PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2014, VOL 7, 2014,
- [26] Fracture Mechanics Analyses of Reactor Pressure Vessel under Pressurized Thermal Shock with TRACE Input Loads 28TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2019), 2019,
- [28] DEVELOPMENT OF PROBABILISTIC FRACTURE MECHANICS ANALYSIS CODE PASCAL VERSION 4 FOR REACTOR PRESSURE VESSELS PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 1B, 2019,
- [29] COUPLING OF NEUTRON TRANSPORT AND PROBABILISTIC FRACTURE MECHANICS CODES FOR ANALYSIS OF EMBRITTLED REACTOR PRESSURE VESSELS PROCEEDINGS OF THE ASME 2020 PRESSURE VESSELS & PIPING CONFERENCE (PVP2020), VOL 3, 2020,