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Investigation of Natural Convection in Heat Generating Molten Nuclear Fuel and Assessment of Core Damage Propagation
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Total instantaneous blockage (TIB) is a severe subassembly accident in a sodium cooled fast reactor. During such an accident, a heat generating fuel pool is formed which is bounded by six neighboring subassemblies which ...
Thermal Analysis of Irradiated Fuel Subassemblies and Fuel Pins During Storage in Concrete Pits of Head End Facility
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Irradiated fuel subassembly (SA)/fuel pins, with significant decay heat are transported from reactor and stored in hot cells (HCs) before reprocessing. During transportation they are heavily shielded and no forced cooling ...
Asymptotic Crack Size of a Prototype Sized Pipe Bend and Comparison With A16 Master Curve
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In the design of a fast breeder reactor (FBR) piping system, asymptotic crack size (2Cs) is traditionally estimated using the leak-before-break (LBB) master curve given in RCC MRx A16. The current approach is seen not to ...
Porous Body Model Based Parametric Study for Sodium to Air Heat Exchanger Used in Fast Reactors
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Sodium to air heat exchangers (AHX) with finned tubes is used in fast breeder reactors for decay heat removal. The aim of decay heat removal is to maintain the fuel, clad, coolant, and structural temperatures within safety ...