Experimental Breeder Reactor II

E105394

Experimental Breeder Reactor II was a sodium-cooled fast breeder nuclear reactor and research facility in Idaho that played a key role in demonstrating advanced reactor safety and fuel cycle technologies.

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Experimental Breeder Reactor II canonical 2

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Predicate Object
instanceOf integral fast reactor prototype
nuclear research reactor
power-producing test reactor
sodium-cooled fast breeder reactor
constructionStart 1958
coolant liquid sodium
coreConfiguration heterogeneous core with driver and blanket assemblies
country United States of America
surface form: United States
decommissioningStart mid-1990s
designOrganization Argonne National Laboratory
electricalPower ~20 megawatts electric
firstCriticality 1964
fuelCycleFeature demonstration of breeding and recycling of plutonium
on-site fuel reprocessing
pyroprocessing of metallic fuel
fuelType metallic uranium-plutonium-zirconium alloy fuel
mixed oxide fuel (MOX) in some tests
gridConnection connected to the electric grid
legacy influenced later advanced reactor and fast reactor designs
location Idaho
Idaho National Engineering Laboratory
surface form: Idaho National Laboratory site
neutronSpectrum fast
notableContribution demonstrated feasibility of metal-fueled fast reactor with inherent safety characteristics
provided experimental basis for passive safety claims of fast reactors
operator Argonne National Laboratory
predecessor Experimental Breeder Reactor I
purpose demonstrate advanced reactor safety
demonstrate closed fuel cycle technologies
demonstrate fast breeder reactor technology
support integral fast reactor program
reactorType pool-type reactor
regulatoryContext operated under U.S. Department of Energy oversight
researchUse fuel cycle technology development
fuel performance testing
materials irradiation testing
reactor safety experiments
safetyDemonstration unprotected loss-of-flow test in 1986
unprotected loss-of-heat-sink test in 1986
safetyFeature passive decay heat removal via natural circulation of sodium
pool-type primary system with large thermal inertia
safetyTestResult reactor shut down safely without operator action or active systems
shutdownDate 1994
sodiumInventory large primary sodium pool surrounding core
startOfOperation 1964
status permanently shut down
under decommissioning and cleanup
successorConcept Integral Fast Reactor concept
thermalPower ~62.5 megawatts thermal

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Idaho National Engineering Laboratory hasFacility Experimental Breeder Reactor II
Experimental Breeder Reactor I successor Experimental Breeder Reactor II