A criterion for predicting thermal stratification due to high-pressure injection in a circulating reactor loop
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:7071912
A physically based criterion for predicting thermal stratification due to high-pressure injection in the presence of loop flow is presented. The predictions are consistent with the CREARE 1/5 scale, CREARE 1/2 scale, and HDR test results.
- Research Organization:
- Purdue Univ., School of Nuclear Engineering, West Lafayette, IN 47907
- OSTI ID:
- 7071912
- Journal Information:
- Nucl. Sci. Eng.; (United States), Vol. 94:1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HDR REACTOR
HIGH PRESSURE COOLANT INJECTION
THERMAL SHOCK
CIRCULATING SYSTEMS
FLOW MODELS
FORECASTING
SCALE MODELS
STRATIFICATION
BWR TYPE REACTORS
ECCS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
MATHEMATICAL MODELS
REACTOR PROTECTION SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
STRUCTURAL MODELS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HDR REACTOR
HIGH PRESSURE COOLANT INJECTION
THERMAL SHOCK
CIRCULATING SYSTEMS
FLOW MODELS
FORECASTING
SCALE MODELS
STRATIFICATION
BWR TYPE REACTORS
ECCS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
MATHEMATICAL MODELS
REACTOR PROTECTION SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
STRUCTURAL MODELS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled