Advances in metallic nuclear fuel
Journal Article
·
· J. Met.; (United States)
Metallic nuclear fuels have generated renewed interest for advanced liquid metal reactors (LMRs) due to their physical properties, ease of fabrication, irradiation behavior, and simple reprocessing. Irradiation performance for both steady-state and transient operations is excellent. Ongoing irradiation tests in Argonne-West's Idaho-based Experimental Breeder Reactor II (EBR-II) have surpassed 100,000 MWd/T burnup and are on their way to a lifetime burnup of 150,000 MWd/T or greater. Metallic fuel also has a unique neutronic characteristic that enables benign reactor responses to loss-of-flow without scram and loss-of-heat-sink without scram accident conditions. This inherent safety potential of metallic fuel was demonstrated in EBR-II just one year ago. Safety tests performed in the reactor have also demonstrated that there is ample margin to fuel element cladding failure under transient overpower conditions. These metallic fuel attributes are key ingredients of the integral fast reactor (IFR) concept being developed at Argonne National Laboratory.
- Research Organization:
- Fuels Technology in the Experimental Breeder Reactor II (EBR-II) Div. of Argonne National Lab.
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6559649
- Journal Information:
- J. Met.; (United States), Journal Name: J. Met.; (United States) Vol. 39:4; ISSN JOMTA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050700 -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
ANL
BREEDER REACTORS
BURNUP
EBR-2 REACTOR
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
FLUIDS
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
FUELS
IRRADIATION
KINETICS
LIQUID METAL COOLED REACTORS
LIQUID METALS
LIQUIDS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATERIALS
METALS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
PERFORMANCE TESTING
PHYSICAL PROPERTIES
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR KINETICS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
REPROCESSING
RESEARCH AND TEST REACTORS
SAFETY
SEPARATION PROCESSES
SODIUM COOLED REACTORS
STEADY-STATE CONDITIONS
TESTING
TRANSIENT OVERPOWER ACCIDENTS
TRANSIENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
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ACCIDENTS
ANL
BREEDER REACTORS
BURNUP
EBR-2 REACTOR
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
FLUIDS
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
FUELS
IRRADIATION
KINETICS
LIQUID METAL COOLED REACTORS
LIQUID METALS
LIQUIDS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATERIALS
METALS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
PERFORMANCE TESTING
PHYSICAL PROPERTIES
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR KINETICS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
REPROCESSING
RESEARCH AND TEST REACTORS
SAFETY
SEPARATION PROCESSES
SODIUM COOLED REACTORS
STEADY-STATE CONDITIONS
TESTING
TRANSIENT OVERPOWER ACCIDENTS
TRANSIENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS