Analysis of the Loading of the PWR Reactor Control Rod Elements in Operating Conditions

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1983-08-22T00:00:00+00:00

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C - Structural Analysis of Fuel, Cladding and Assemblies
C6 - Thermal Reactor Fuel Assemblies and Core Components
SMiRT 7 - Chicago, USA. August 22-26, 1983

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IASMiRT

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