Loss-of-Fluid Test Facility

E99197

The Loss-of-Fluid Test Facility is a specialized experimental installation used to study and simulate loss-of-coolant and related accident scenarios in nuclear reactors.

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AI-generated illustration of Loss-of-Fluid Test Facility

This AI-generated illustration was produced by black-forest-labs/FLUX.2-dev (1024x1024) from a prompt written by openai/gpt-oss-120b from the entity's label + description.

Prompt

Generate an image of the Loss-of-Fluid Test Facility (The Loss-of-Fluid Test Facility is a specialized experimental installation used to study and simulate loss-of-coolant and related accident scenarios in nuclear reactors.)

All labels observed (1)

Label Occurrences
Loss-of-Fluid Test Facility canonical 1

How this entity was disambiguated

Statements (45)

Predicate Object
instanceOf experimental facility ⓘ
nuclear safety research facility ⓘ
thermal-hydraulic test facility ⓘ
aimsTo improve predictive capability of thermal-hydraulic models ⓘ
reduce uncertainties in reactor safety analysis ⓘ
contributesTo development of safety standards for nuclear power plants ⓘ
understanding of nuclear reactor accident progression ⓘ
validation of best-estimate thermal-hydraulic codes ⓘ
dataUsedBy nuclear regulators ⓘ
nuclear safety analysts ⓘ
reactor designers ⓘ
field nuclear engineering ⓘ
reactor safety ⓘ
thermal-hydraulics ⓘ
hasCharacteristic capable of high-pressure and high-temperature operation ⓘ
instrumented for detailed thermal-hydraulic measurements ⓘ
scaled representation of reactor coolant system components ⓘ
measures mass flow rates ⓘ
pressure distributions ⓘ
temperature distributions ⓘ
void fractions in two-phase flow ⓘ
purpose provide experimental data for code validation ⓘ
simulate reactor accident transients ⓘ
study loss-of-coolant accident scenarios in nuclear reactors ⓘ
support development of emergency core cooling system designs ⓘ
relatedTo emergency core cooling system performance ⓘ
loss-of-coolant accident analysis ⓘ
nuclear power plant safety assessment ⓘ
researchFocus blowdown and reflood phenomena ⓘ
loss-of-coolant accidents ⓘ
reactor system thermal-hydraulic behavior ⓘ
safety system performance under accident conditions ⓘ
two-phase flow in reactor systems ⓘ
simulates breaks in reactor coolant system piping ⓘ
depressurization of reactor coolant systems ⓘ
emergency core cooling system injection conditions ⓘ
loss-of-coolant transients ⓘ
supports development of accident management strategies ⓘ
improvement of reactor safety systems ⓘ
typeOfTests integral system tests ⓘ
transient thermal-hydraulic tests ⓘ
two-phase flow experiments ⓘ
usedFor benchmarking of system thermal-hydraulic computer codes ⓘ
evaluation of nuclear reactor safety margins ⓘ
supporting regulatory safety analyses ⓘ

How these facts were elicited

Referenced by (1)

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

Idaho National Engineering Laboratory → hasFacility → Loss-of-Fluid Test Facility ⓘ