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 1

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 of America
surface form: 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 NERFINISHED
National Reactor Testing Station NERFINISHED
locationCountry United States of America
surface form: United States
moderator light water
neutronSpectrum thermal
operator United States Atomic Energy Commission NERFINISHED
partOf SPERT program NERFINISHED
programGoal develop safety criteria for power reactors
improve understanding of reactor kinetics
validate reactor dynamics models
reactorType light-water moderated reactor
relatedTo SPERT-I NERFINISHED
SPERT-III NERFINISHED
SPERT-IV NERFINISHED
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 (1)

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