Thermal aspects in the design of an HTGR fuel reprocessing plant
Conference
·
OSTI ID:5912681
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 principal 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.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- OSTI ID:
- 5912681
- Report Number(s):
- GA-A-15487; CONF-790822-9
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
DESIGN
ENERGY SOURCES
FUEL REPROCESSING PLANTS
FUELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR FUELS
REACTOR MATERIALS
REACTORS
REPROCESSING
SEPARATION PROCESSES
SPENT FUELS
TEMPERATURE EFFECTS
THOREX PROCESS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
DESIGN
ENERGY SOURCES
FUEL REPROCESSING PLANTS
FUELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR FUELS
REACTOR MATERIALS
REACTORS
REPROCESSING
SEPARATION PROCESSES
SPENT FUELS
TEMPERATURE EFFECTS
THOREX PROCESS