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Transition boiling heat transfer in the Semiscale MOD-3 core during reflood

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:6921528
;
Transition boiling heat transfer data from Semiscale Mod-3 gravity feed reflood experiments have been compared to existing transition boiling correlations. The existing correlations were found to be inadequate for predicting the Semiscale rod bundle data; therefore, a new correlation for transition boiling was developed. The new correlation is applicable for boiling water with stainless steel, electrically heated vertical rods in a pressure range of 138 to 414 kPa. When the new transition boiling correlation is combined with the Berenson film boiling correlation, a good fit to Semiscale reflood data results.
Research Organization:
EG and G Idaho, Inc. Idaho National Engineering Laboratory, Idaho Falls, Idaho 83415
OSTI ID:
6921528
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 56:3; ISSN NUTYB
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ALLOYS
ANALOG SYSTEMS
BOILING
CHROMIUM ALLOYS
CORE FLOODING SYSTEMS
CORRELATIONS
CORROSION RESISTANT ALLOYS
DATA
ECCS
ELECTRIC HEATING
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EXPERIMENTAL DATA
FILM BOILING
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
FUEL RODS
FUNCTIONAL MODELS
HEAT TRANSFER
HEATING
HYDROGEN COMPOUNDS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
LOW PRESSURE
NUMERICAL DATA
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTOR SIMULATORS
REACTORS
SCALE MODELS
SIMULATORS
STAINLESS STEELS
STEELS
STRUCTURAL MODELS
TRANSITION BOILING
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS