|
gptkbp:instanceOf
|
gptkb:nuclear_reactor
|
|
gptkbp:coolingSystem
|
liquid sodium
|
|
gptkbp:country
|
gptkb:United_States
|
|
gptkbp:criticalFor
|
1964
|
|
gptkbp:decommissioned
|
1994
|
|
gptkbp:designedBy
|
gptkb:Argonne_National_Laboratory
|
|
gptkbp:electricPower
|
20 MW
|
|
gptkbp:fuelType
|
metallic uranium fuel
|
|
gptkbp:fullName
|
gptkb:Experimental_Breeder_Reactor_II
|
|
https://www.w3.org/2000/01/rdf-schema#label
|
EBR-II
|
|
gptkbp:location
|
gptkb:Idaho_National_Laboratory
|
|
gptkbp:notableFeature
|
demonstrated inherent safety features
integral fuel reprocessing facility
|
|
gptkbp:notableMission
|
passive safety demonstration in 1986
|
|
gptkbp:operatedBy
|
gptkb:Argonne_National_Laboratory
|
|
gptkbp:predecessor
|
gptkb:EBR-I
|
|
gptkbp:purpose
|
demonstrate breeder reactor technology
demonstrate integral fast reactor concept
|
|
gptkbp:reactorCore
|
pool-type design
|
|
gptkbp:status
|
decommissioned
|
|
gptkbp:successor
|
gptkb:Integral_Fast_Reactor_(IFR)_program
|
|
gptkbp:thermalCapacity
|
62.5 MW
|
|
gptkbp:type
|
sodium-cooled fast reactor
|
|
gptkbp:usedFor
|
nuclear fuel cycle research
demonstration of closed fuel cycle
|
|
gptkbp:bfsParent
|
gptkb:first_breeder_reactor_(EBR-I)
|
|
gptkbp:bfsLayer
|
6
|