Analysis of the master curve approach on the fracture toughness properties of SA508 Gr.4N Ni–Mo–Cr low alloy steels for reactor pressure vessels
Author:
Publisher
Elsevier BV
Subject
Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science
Reference26 articles.
1. Neutron irradiation embrittlement of ASME SA508, C1.3 steel
2. Master curve techniques to evaluate an irradiation embrittlement of nuclear reactor pressure vessels for a long-term operation
3. A comparison of fracture behavior of low alloy steel with different sizes of carbide particles
4. On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels
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2. Investigation of Residual Stress Effect on Cleavage Fracture Toughness in the Transition Temperature Region by Considering the Crack-Tip Constraint;Journal of Materials Engineering and Performance;2024-07-24
3. Effect of austenitizing temperature on martensitic transformation in SA508Gr.4N steel;Journal of Materials Science & Technology;2024-07
4. Research Progress of Steels for Nuclear Reactor Pressure Vessels;Materials;2022-12-08
5. Mechanical and fatigue properties of SA508-IV steel used for nuclear reactor pressure vessels;Journal of Iron and Steel Research International;2022-02-25
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