SPERT-IV
E442872
SPERT-IV was a research reactor facility used in the SPERT program to study reactor safety and transient behavior under power excursion conditions.
All labels observed (2)
| Label | Occurrences |
|---|---|
| SPERT-IV canonical | 4 |
| SPERT program | 1 |
How this entity was disambiguated
This entity first appeared as the object of triple T4384102 — 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: SPERT-IV Context triple: [Special Power Excursion Reactor Test series, hasPart, SPERT-IV]
-
A.
SPERT-I
SPERT-I was the first reactor in the Special Power Excursion Reactor Test series, designed to study reactor safety and behavior under rapid power excursion conditions.
-
B.
SPERT-II
SPERT-II was a research nuclear reactor used in the SPERT program to study reactor safety and power excursion behavior under experimental conditions.
-
C.
SPERT-III
SPERT-III was a U.S. experimental nuclear research reactor used in the mid-20th century to study reactor safety and power excursion behavior.
-
D.
SPICE
SPICE is Amazon QuickSight’s in-memory calculation and storage engine designed to enable fast, scalable, and interactive data analysis.
-
E.
SAS-4
SAS-4 is the fourth-generation Serial Attached SCSI (SAS) interface standard that significantly increases data transfer speeds and bandwidth for enterprise storage systems.
- 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: SPERT-IV Target entity description: SPERT-IV was a research reactor facility used in the SPERT program to study reactor safety and transient behavior under power excursion conditions.
-
A.
SPERT-I
SPERT-I was the first reactor in the Special Power Excursion Reactor Test series, designed to study reactor safety and behavior under rapid power excursion conditions.
-
B.
SPERT-II
SPERT-II was a research nuclear reactor used in the SPERT program to study reactor safety and power excursion behavior under experimental conditions.
-
C.
SPERT-III
SPERT-III was a U.S. experimental nuclear research reactor used in the mid-20th century to study reactor safety and power excursion behavior.
-
D.
SPICE
SPICE is Amazon QuickSight’s in-memory calculation and storage engine designed to enable fast, scalable, and interactive data analysis.
-
E.
SAS-4
SAS-4 is the fourth-generation Serial Attached SCSI (SAS) interface standard that significantly increases data transfer speeds and bandwidth for enterprise storage systems.
- F. None of above. chosen
Statements (31)
| Predicate | Object |
|---|---|
| instanceOf |
nuclear research reactor
ⓘ
research reactor facility ⓘ |
| coolant | light water ⓘ |
| country |
United States
ⓘ
linked to:
United States of America
|
| designedFor |
reactivity insertion experiments
ⓘ
safety-related transient tests ⓘ |
| fuelMaterial | enriched uranium ⓘ |
| fuelType | plate-type fuel ⓘ |
| location |
Idaho
ⓘ
National Reactor Testing Station ⓘ
linked to:
Idaho National Engineering Laboratory
|
| moderator | light water ⓘ |
| neutronSpectrum | thermal ⓘ |
| operator | Phillips Petroleum Company ⓘ |
| partOf |
SPERT program
ⓘ
linked to:
SPERT-IV
United States nuclear safety research program ⓘ |
| programFocus |
reactor kinetics
ⓘ
reactor protection system performance ⓘ reactor stability ⓘ |
| purpose |
power excursion experiments
ⓘ
study of reactor safety ⓘ study of transient reactor behavior ⓘ |
| researchArea |
nuclear reactor safety
ⓘ
reactivity accident behavior ⓘ |
| safetyObjective |
define safe operating limits for power excursions
ⓘ
understand conditions leading to fuel damage ⓘ |
| successorTo |
SPERT-I
ⓘ
SPERT-II ⓘ SPERT-III ⓘ |
| usedIn |
development of reactor safety criteria
ⓘ
evaluation of power excursion behavior ⓘ validation of reactor transient analysis methods ⓘ |
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: SPERT-IV Description of subject: SPERT-IV was a research reactor facility used in the SPERT program to study reactor safety and transient behavior under power excursion conditions.
Referenced by (5)
Full triples — surface form annotated when it differs from this entity's canonical label.