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 (1)
| Label | Occurrences |
|---|---|
| SPERT-IV canonical | 1 |
Statements (31)
| Predicate | Object |
|---|---|
| instanceOf |
nuclear research reactor
ⓘ
research reactor facility ⓘ |
| coolant | light water ⓘ |
| country |
United States of America
ⓘ
surface form:
United States
|
| designedFor |
reactivity insertion experiments
ⓘ
safety-related transient tests ⓘ |
| fuelMaterial | enriched uranium ⓘ |
| fuelType | plate-type fuel ⓘ |
| location |
Idaho
NERFINISHED
ⓘ
National Reactor Testing Station NERFINISHED ⓘ |
| moderator | light water ⓘ |
| neutronSpectrum | thermal ⓘ |
| operator | Phillips Petroleum Company NERFINISHED ⓘ |
| partOf |
SPERT program
NERFINISHED
ⓘ
United States nuclear safety research program NERFINISHED ⓘ |
| 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
NERFINISHED
ⓘ
SPERT-II NERFINISHED ⓘ SPERT-III NERFINISHED ⓘ |
| usedIn |
development of reactor safety criteria
ⓘ
evaluation of power excursion behavior ⓘ validation of reactor transient analysis methods ⓘ |
Referenced by (1)
Full triples — surface form annotated when it differs from this entity's canonical label.