Experimental Breeder Reactor II
E105394
integral fast reactor prototype
nuclear research reactor
power-producing test reactor
sodium-cooled fast breeder reactor
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.
All labels observed (2)
| Label | Occurrences |
|---|---|
| Experimental Breeder Reactor II canonical | 2 |
| National Reactor Testing Station experimental reactor fleet | 1 |
How this entity was disambiguated
This entity first appeared as the object of triple T854081 — resolving that mention is where its identity was fixed. The disambiguator weighed these candidate entities and picked the highlighted one (or “None”, minting a new entity). This is how homonymy is resolved: the same surface form can point to different entities.
NED1
Entity disambiguation (via context triple)
gpt-5-mini-2025-08-07
Target entity: Experimental Breeder Reactor II Context triple: [Idaho National Engineering Laboratory, hasFacility, Experimental Breeder Reactor II]
-
A.
Experimental Breeder Reactor I
Experimental Breeder Reactor I was the world’s first nuclear reactor to produce usable electricity, marking a major milestone in nuclear power development.
-
B.
X-10 graphite reactor
The X-10 graphite reactor was an early nuclear reactor at Oak Ridge, Tennessee, built during the Manhattan Project as a pilot plant for plutonium production and a key step toward the development of nuclear weapons and nuclear energy.
-
C.
TRIGA research reactor
The TRIGA research reactor is a small, inherently safe nuclear reactor design widely used in universities and research institutions for education, training, and scientific experiments.
-
D.
Chicago Pile-2
Chicago Pile-2 was an early research nuclear reactor built at the Argonne site to continue and expand experimental work following the first controlled chain reaction achieved by Chicago Pile-1.
-
E.
Chicago Pile-1
Chicago Pile-1 was the world’s first artificial nuclear reactor, achieving the first controlled, self-sustaining nuclear chain reaction in 1942 under the leadership of Enrico Fermi.
- F. None of above. chosen
- G. Unsure - the case is ambiguous/there is not enough information to decide.
NED2
Entity disambiguation (via description)
gpt-5-mini-2025-08-07
Target entity: Experimental Breeder Reactor II Target entity description: 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.
-
A.
Experimental Breeder Reactor I
Experimental Breeder Reactor I was the world’s first nuclear reactor to produce usable electricity, marking a major milestone in nuclear power development.
-
B.
X-10 graphite reactor
The X-10 graphite reactor was an early nuclear reactor at Oak Ridge, Tennessee, built during the Manhattan Project as a pilot plant for plutonium production and a key step toward the development of nuclear weapons and nuclear energy.
-
C.
TRIGA research reactor
The TRIGA research reactor is a small, inherently safe nuclear reactor design widely used in universities and research institutions for education, training, and scientific experiments.
-
D.
Chicago Pile-2
Chicago Pile-2 was an early research nuclear reactor built at the Argonne site to continue and expand experimental work following the first controlled chain reaction achieved by Chicago Pile-1.
-
E.
Chicago Pile-1
Chicago Pile-1 was the world’s first artificial nuclear reactor, achieving the first controlled, self-sustaining nuclear chain reaction in 1942 under the leadership of Enrico Fermi.
- F. None of above. chosen
Statements (48)
| 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
ⓘ
linked to:
United States of America
|
| 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 Laboratory site ⓘ
linked to:
Idaho National Engineering Laboratory
|
| 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 ⓘ |
How these facts were elicited
The pipeline generated the facts above by prompting gpt-5.1 with this entity's name + description and the instruction below.
Instruction
You are a knowledge base construction expert. Given a subject entity and a description of it, return factual statements that you know for the subject as a JSON list of dictionaries(triples), where keys must be "subject", "predicate" and "object". The number of facts may be very high, between 25 to 50 or more, for very popular subjects. For less popular subjects, the number of facts can be very low, like 5 or 10. # Requirements - If you don't know the subject at all, return an empty list. - If the subject is not a named entity, return an empty list. - Include at least one triple where predicate is "instanceOf". - Do not get too wordy. - Separate several objects into multiple triples with one object.
Input
Subject: Experimental Breeder Reactor II Description of subject: 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.
Referenced by (3)
Full triples — surface form annotated when it differs from this entity's canonical label.