
doi: 10.2172/7351938
The report describes the machine solution of a large number (approximately 52,000) of simultaneous linear algebraic equations in which the unknowns are the concentrations of nuclides in the fuel salt of a fluid-fueled reactor (MSBR) having a continuous fuel processing plant. Most of the equations define concentrations at various points in the processing plant. The code allows as input a generalized description of a processing plant flowsheet; it also performs the iterative adjustment of flowsheet parameters for determination of concentrations throughout the flowsheet, and the associated effect of the specified processing mode on the overall reactor operation.
Mathematical Models, Computer Codes, Reactor Materials, Breeder Reactors, Liquid Fuels, Fuels, Breeding, Molten Salt Fueled Reactors, 21 Specific Nuclear Reactors And Associated Plants, Molten Salt Reactors, 11 Nuclear Fuel Cycle And Fuel Materials, Reactors, Reprocessing, Separation Processes 210500* -- Power Reactors, Nuclear Fuels, Fuel Cycle, Molten Salt Fuels, Energy Sources, Fluid Fueled Reactors, M Codes, 050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
Mathematical Models, Computer Codes, Reactor Materials, Breeder Reactors, Liquid Fuels, Fuels, Breeding, Molten Salt Fueled Reactors, 21 Specific Nuclear Reactors And Associated Plants, Molten Salt Reactors, 11 Nuclear Fuel Cycle And Fuel Materials, Reactors, Reprocessing, Separation Processes 210500* -- Power Reactors, Nuclear Fuels, Fuel Cycle, Molten Salt Fuels, Energy Sources, Fluid Fueled Reactors, M Codes, 050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
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