Modeling and analysis of low heat flux natural convection sodium boiling in LMFBRs
Flow excursion induced dryout at low heat flux natural convection boiling, typical of liquid metal fast breeder reactor, is addressed. Steady state calculations indicate that low quality boiling is possible up to the point of Ledinegg instability leading to flow excursion and subsequent dryout in agreement with experimental data. A flow regime-dependent dryout heat flux relationship based upon saturated boiling criterion is also presented. Transient analysis indicates that premature flow excursion can not be ruled out and sodium boiling is highly transient dependent. Analysis of a high heat flux forced convection, loss-of-flow transient shows a significantly faster flow excursion leading to dryout in excellent agreement with parallel calculations using the two-dimensional THORAX code. 31 refs., 25 figs., 6 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5341469
- Report Number(s):
- NUREG/CR-2006; BNL-NUREG-51541; ON: TI83010683
- Country of Publication:
- United States
- Language:
- English
Similar Records
Flow excursion-induced dryout at low heat flux natural convection boiling
Flow-excursion-induced dryout at low-heat-flux
THORAX pretest prediction of a sodium-boiling transient in a 19-pin simulated LMFBR driver bundle
Journal Article
·
Thu May 01 00:00:00 EDT 1986
· J. Heat Transfer; (United States)
·
OSTI ID:5824786
Flow-excursion-induced dryout at low-heat-flux
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6546149
THORAX pretest prediction of a sodium-boiling transient in a 19-pin simulated LMFBR driver bundle
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6756920
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
BOILING
BREEDER REACTORS
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CONVECTION
DRYOUT
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENTS
FUEL PINS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF COOLANT
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
METALS
NATURAL CONVECTION
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SIMULATION
SODIUM
TWO-DIMENSIONAL CALCULATIONS
TWO-PHASE FLOW
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
BOILING
BREEDER REACTORS
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CONVECTION
DRYOUT
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENTS
FUEL PINS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF COOLANT
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
METALS
NATURAL CONVECTION
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SIMULATION
SODIUM
TWO-DIMENSIONAL CALCULATIONS
TWO-PHASE FLOW