Development of the Material Strength Standard of 316FR steel and Modified 9Cr-1Mo steel for Next-generation Fast Reactor in Japan

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2024-03-03

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Division 6 - Design Issues, Codes and Standards
Division 6-We.2.C - Creep/fatigue design and flaw evaluation(2)
00 - SMiRT 27 - Yokohama, Japan. March 3-8, 2024

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IASMiRT

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