SPERT-II

E437254

SPERT-II was a research nuclear reactor used in the SPERT program to study reactor safety and power excursion behavior under experimental conditions.

All labels observed (1)

Label Occurrences
SPERT-II canonical 4

How this entity was disambiguated

Statements (36)

Predicate Object
instanceOf research nuclear reactor ⓘ
test reactor ⓘ
conductedExperimentsOn control rod ejection scenarios ⓘ
coolant temperature effects on reactivity ⓘ
prompt critical excursions ⓘ
reactivity step insertions ⓘ
coolant light water ⓘ
country United States ⓘ
dataUsedBy nuclear regulatory bodies ⓘ
reactor safety analysts ⓘ
dataUsedFor development of design-basis accident criteria ⓘ
validation of reactor safety codes ⓘ
designedFor rapid power transients ⓘ
reactivity insertion experiments ⓘ
field nuclear engineering ⓘ
reactor safety research ⓘ
hasPurpose study power excursion behavior ⓘ
study reactor safety ⓘ
location Idaho ⓘ
National Reactor Testing Station ⓘ
locationCountry United States ⓘ
moderator light water ⓘ
neutronSpectrum thermal ⓘ
operator United States Atomic Energy Commission ⓘ
partOf SPERT program ⓘ
programGoal develop safety criteria for power reactors ⓘ
improve understanding of reactor kinetics ⓘ
validate reactor dynamics models ⓘ
reactorType light-water moderated reactor ⓘ
relatedTo SPERT-I ⓘ
SPERT-III ⓘ
SPERT-IV ⓘ
safetyFocus power excursion behavior ⓘ
reactor stability under abnormal conditions ⓘ
usedFor safety experiments under controlled conditions ⓘ
transient testing of reactor cores ⓘ

How these facts were elicited

Referenced by (4)

Full triples — surface form annotated when it differs from this entity's canonical label.

SPERT-IV → successorTo → SPERT-II ⓘ
SPERT-I → successor → SPERT-II ⓘ
SPERT-III → precededBy → SPERT-II ⓘ