Some Comments on the Treatment of Thermal Stresses in the ASME Nuclear Vessel Code

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F3-2.pdf (430.09 KB)

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1975

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F - Structural Analysis of Reactor Core and Coolant Circuit Structures
F3 - Structural Analysis of Pipework Systems
SMiRT 3 - London, UK. 1975

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IASMiRT

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http://www.lib.ncsu.edu/resolver/1840.20/28227

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1975 - SMiRT 3 - London, UK