
Abstract HTGR graphite-based spent fuel has been thermally analyzed to provide data for a reprocessing design. Steps include crushing, burning in fluidized beds, size classification, dissolution, and solvent extraction. The prinicipal problem is that the bunkers holding feed and product between steps need sizing for decay heat. Constraints have been set for different modes of cooling. However, criticality may prove stricter. Adverse effects of solvent degradation products in the Acid-Thorex process, mainly dibutyl phosphate (DBP), are reduced by using a partition flowsheet and by adding fluoride ions to the 1BX and 1CX columns.
Design, Reactor Materials, Separation Processes 050800* -- Nuclear Fuels-- Spent Fuels Reprocessing, Thorex Process, Fuels, Reactors, 11 Nuclear Fuel Cycle And Fuel Materials, Reprocessing, Temperature Effects, Gas Cooled Reactors, Nuclear Facilities, Graphite Moderated Reactors, Nuclear Fuels, Fuel Reprocessing Plants, Energy Sources, Htgr Type Reactors, Spent Fuels
Design, Reactor Materials, Separation Processes 050800* -- Nuclear Fuels-- Spent Fuels Reprocessing, Thorex Process, Fuels, Reactors, 11 Nuclear Fuel Cycle And Fuel Materials, Reprocessing, Temperature Effects, Gas Cooled Reactors, Nuclear Facilities, Graphite Moderated Reactors, Nuclear Fuels, Fuel Reprocessing Plants, Energy Sources, Htgr Type Reactors, Spent Fuels
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