Analysis of Prestressed Concrete Reactor Vessels Under High Thermal Gradient

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H2-4.pdf (323.19 KB)

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1975

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H - Structural Analysis of Prestressed Concrete Reactor Pressure Vessels
H2 - Structural Analysis I
SMiRT 3 - London, UK. 1975

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IASMiRT

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http://www.lib.ncsu.edu/resolver/1840.20/28323

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1975 - SMiRT 3 - London, UK