Creep-Fatigue Crack Propagation In Current International Codes For Components At Elevated Temperatures In Nuclear Engineering: Comparison, Programming And Case Study

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Creep-Fatigue_Crack_Propagation_In_Current_International_Codes_For_Components_At_Elevated_Temperatures_In_Nuclear_Engineering_Comparison,_Programming_And_Case_Study.pdf (425.95 KB)

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2019-08-04

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D6 - DESIGN ISSUES, CODES AND STANDARDS
D6-S3 - Fatigue and Thermal Design
00 - SMiRT 25 - Charlotte, USA. August 4-9, 2019

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IASMiRT

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https://www.lib.ncsu.edu/resolver/1840.20/37856

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2019 - SMiRT 25 - Charlotte, USA