Comparison of one-and-two-dimensional sodium boiling models
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5625583
None
- Research Organization:
- Oak Ridge National Laboratory, Oak Ridge, TN 37830
- OSTI ID:
- 5625583
- Report Number(s):
- CONF-830609-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 44
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220200* -- Nuclear Reactor Technology-- Components & Accessories
ACCIDENTS
ALKALI METALS
BOILING
COMPARATIVE EVALUATIONS
COMPRESSIBLE FLOW
COMPUTER CODES
COMPUTERIZED SIMULATION
DRYOUT
ELEMENTS
EXCURSIONS
FLOW MODELS
FLUID FLOW
FRICTION FACTOR
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
FUEL PINS
FUEL-COOLANT INTERACTIONS
IN PILE LOOPS
L CODES
LIQUID METAL COOLED REACTORS
MATHEMATICAL MODELS
METALS
ONE-DIMENSIONAL CALCULATIONS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR SAFETY EXPERIMENTS
REACTORS
SIMULATION
SODIUM
SODIUM COOLED REACTORS
T CODES
TWO-DIMENSIONAL CALCULATIONS
TWO-PHASE FLOW
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220200* -- Nuclear Reactor Technology-- Components & Accessories
ACCIDENTS
ALKALI METALS
BOILING
COMPARATIVE EVALUATIONS
COMPRESSIBLE FLOW
COMPUTER CODES
COMPUTERIZED SIMULATION
DRYOUT
ELEMENTS
EXCURSIONS
FLOW MODELS
FLUID FLOW
FRICTION FACTOR
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
FUEL PINS
FUEL-COOLANT INTERACTIONS
IN PILE LOOPS
L CODES
LIQUID METAL COOLED REACTORS
MATHEMATICAL MODELS
METALS
ONE-DIMENSIONAL CALCULATIONS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR SAFETY EXPERIMENTS
REACTORS
SIMULATION
SODIUM
SODIUM COOLED REACTORS
T CODES
TWO-DIMENSIONAL CALCULATIONS
TWO-PHASE FLOW