Advanced test reactor countercurrent flow experiment
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:6371584
- Idaho National Engineering Lab., Idaho Falls (USA)
A series of countercurrent flow limiting (CCFL) experiments in a small-scale hydraulic facility at Idaho National Engineering Laboratory have recently been completed. The experiments were carried out in thin rectangular flow channels (0.001 {times} 0.064 {times} 1.4 m) representative of the flow gaps between adjacent fuel assemblies in the core of the advanced test reactor (ATR). The primary objective of this study was to collect CCFL experimental data under conditions postulated for a hypothetical large-break loss-of-coolant accident and to compare the data with existing CCFL correlations. In case of such an accident, the emergency core cooling systems reflood the reactor core and provide coolant for the flow channel between the side plates through either the top or the bottom of the flow channel. However, along the flow channel passage, the flow of coolant may be limited by upflowing steam generated from water vaporization, such as in the countercurrent flow limit.
- OSTI ID:
- 6371584
- Report Number(s):
- CONF-900608--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 61
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATR REACTOR
COUNTER CURRENT
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
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IDAHO NATIONAL ENGINEERING LABORATORY
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LOSS OF COOLANT
MATERIALS TESTING REACTORS
MECHANICS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY EXPERIMENTS
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RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATR REACTOR
COUNTER CURRENT
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
IDAHO NATIONAL ENGINEERING LABORATORY
IRRADIATION REACTORS
LOSS OF COOLANT
MATERIALS TESTING REACTORS
MECHANICS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS