Molten Salt Reactor Experiment

URI: https://gptkb.org/entity/Molten_Salt_Reactor_Experiment
GPTKB entity
AI-created image of Molten Salt Reactor Experiment
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Statements (33)
Predicate Object
gptkbp:instanceOf gptkb:nuclear_reactor
gptkbp:closed completion of experimental objectives
gptkbp:coolingSystem molten fluoride salt
gptkbp:country gptkb:United_States
gptkbp:designedBy gptkb:Oak_Ridge_National_Laboratory
gptkbp:endDate 1969
gptkbp:fuelCycle thorium-uranium
gptkbp:fuelType gptkb:uranium-233
uranium-235
gptkbp:hasConcept graphite
https://www.w3.org/2000/01/rdf-schema#label Molten Salt Reactor Experiment
gptkbp:laps single loop
gptkbp:location gptkb:Oak_Ridge_National_Laboratory
gptkbp:notableFor first reactor to use molten salt as both fuel and coolant
demonstrated feasibility of liquid-fueled reactors
gptkbp:operatedBy gptkb:Oak_Ridge_National_Laboratory
gptkbp:operationalTemperature 650°C
gptkbp:predecessor gptkb:Aircraft_Reactor_Experiment
gptkbp:primarySaltComposition LiF-BeF2-ZrF4-UF4
gptkbp:purpose demonstration of molten salt reactor technology
gptkbp:reactorCoreShape cylindrical
gptkbp:reactorType molten salt reactor
gptkbp:researchInterest corrosion behavior of molten salts
fission product removal
liquid-fueled reactor operation
tritium management
gptkbp:startDate 1965
gptkbp:status decommissioned
gptkbp:successor gptkb:Molten_Salt_Breeder_Reactor
gptkbp:thermalCapacity 7.4 MW
gptkbp:usedModerator graphite
gptkbp:bfsParent gptkb:Oak_Ridge_National_Laboratory
gptkbp:bfsLayer 3