Fatigue tests on a ferritic-martensitic steel at 420°C: Comparison between in-situ and postirradiation properties
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OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
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References (14)
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11. Fundamental Aspects of Nuclear Reactor Fuel Elements10.2172/7343826 ↗
12. Fracture and Fatigue Control in Structures
13. Fracture and Fatigue Control in Structures
14. Hobson · 1986 · 441