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Transmutation of LWR High-Level Waste in LMRs

Conference · · Transactions of the American Nuclear Society
OSTI ID:7239978
Past studies have shown that actinide waste discharged from light water reactors (LWRs) could be burned effectively in liquid-metal fast reactor systems. These systems were predominantly mixed plutonium/uranium oxide or metal breeder systems with small percentages of minor actinides. This study illustrates how LWR actinides and fission products could be burned in a minor actinide nitride-fueled advanced liquid-metal reactor (ALMR) that has special moderating assemblies to enhance fission product transmutation. For this study, the reactor was assumed to be only a burner, not a breeder. The model contained a preponderance of minor actinides with only sufficient plutonium to maintain 1-yr fuel cycles. No uranium was loaded because plutonium production was not desired.
Research Organization:
Westinghouse Hanford Co., Richland, WA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
OSTI ID:
7239978
Report Number(s):
CONF-911107--
Conference Information:
Journal Name: Transactions of the American Nuclear Society Journal Volume: 64
Country of Publication:
United States
Language:
English

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Related Subjects

052000* -- Nuclear Fuels-- Waste Management
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210500 -- Power Reactors
Breeding
ACTINIDE BURNER REACTORS
ACTINIDES
ALKALINE EARTH METAL COMPOUNDS
ALLOY NUCLEAR FUELS
Actinide Waste Discharge Burning
Advanced Liquid-Metal Reactor (ALMR)
BURNUP
BWR TYPE REACTORS
CALCIUM COMPOUNDS
CALCIUM HALIDES
CALCIUM IODIDES
CAPTURE
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
CRYSTAL LATTICES
CRYSTAL STRUCTURE
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FISSION PRODUCTS
FUEL ASSEMBLIES
FUEL CYCLE
FUEL MANAGEMENT
FUELS
HALIDES
HALOGEN COMPOUNDS
HEXAGONAL LATTICES
HIGH-LEVEL RADIOACTIVE WASTES
HYDRIDES
HYDROGEN COMPOUNDS
INVENTORIES
IODIDES
IODINE COMPOUNDS
ISOTOPES
LIQUID METAL COOLED REACTORS
Light Water Reactors (LWRs)
MANAGEMENT
MATERIALS
METALS
MIXED NITRIDE FUELS
MIXED OXIDE FUELS
MODERATORS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
O CODES
PHOTON TRANSPORT
POWER REACTORS
PWR TYPE REACTORS
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTES
REACTIVITY
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTORS
SIMULATION
SOLID FUELS
SPENT FUELS
THERMAL REACTORS
TRANSITION ELEMENT COMPOUNDS
TRANSMUTATION
VERIFICATION
VOID FRACTION
WASTE MANAGEMENT
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
YTTRIUM COMPOUNDS
YTTRIUM HYDRIDES