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von Onizawa, Takashi
Veröffentlicht in SMiRT (25. : 2019 : Charlotte, NC) 25th International Conference on Structural Mechanics in Reactor Technology 2019 (SMiRT 25) ; Volume 5 of 5 (2020)

APPLICATION OF FRACTURE CONTROL TO NUCLEAR COMPONENTS FOR MITIGATION OF ACCIDENT CONSEQUENCE

von Kasahara, Naoto
Veröffentlicht in SMiRT (25. : 2019 : Charlotte, NC) 25th International Conference on Structural Mechanics in Reactor Technology 2019 (SMiRT 25) ; Volume 5 of 5 (2020)

PVP2021-61942 Development of Leak Before Break Assessment Guidelines for Sodium Cooled Fast Reactors in Japan

von Yada, Hiroki
Veröffentlicht in ASME Pressure Vessels and Piping Conference (2021 : Online) Proceedings of ASME 2021 Pressure Vessels and Piping Conference (PVP2021) ; Volume 1: Codes and standards (2021)

PVP2020-21072 Application of Fracture Control to Mitigate Failure Consequence Under BDBE

von Kasahara, Naoto
Veröffentlicht in ASME Pressure Vessels & Piping Conference (2020 : Online) Proceedings of the ASME Pressure Vessels & Piping Conference - 2020 ; Volume 3: Design and analysis (2020)

PVP2020-21397 Proposal of Simulation Materials Test Technique and Their Constitutive Equations for Structural Tests and Analyses Simulating Severe Accident Conditions

von Hashidate, Ryuta
Veröffentlicht in ASME Pressure Vessels & Piping Conference (2020 : Online) Proceedings of the ASME Pressure Vessels & Piping Conference - 2020 ; Volume 3: Design and analysis (2020)