Influence of the maximum fatigue-pre-cracking load on Master Curve T0 evaluation concerning the warm-pre-stress effect
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Date
2024-03-03
Advisors
Journal Title
Series/Report No.
Division 2 - Fracture Mechanics and Structural Integrity
Division 2-Tu.2.I - Structural Integrity Assessment of Reactor Pressure Vessel (2)
00 - SMiRT 27 - Yokohama, Japan. March 3-8, 2024
Division 2-Tu.2.I - Structural Integrity Assessment of Reactor Pressure Vessel (2)
00 - SMiRT 27 - Yokohama, Japan. March 3-8, 2024
Journal ISSN
Volume Title
Publisher
IASMiRT
