Transient two-phase channel flow for nonuniform axial heat fluxes
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6832001
The analysis of transients in boiling channels is essential in the evaluation of thermal margin. Indeed, the occurrence of critical heat flux is much more likely during transient conditions than for steady-state operations. This paper presents a closed-form analytical solution for a flow transient in a boiling channel having a nonuniform axial heat flux. Similar solutions have been obtained previously for uniform axial heat flux distribution using homogeneous and drift-flux models. No previous analytical solutions have been published for flow transients in boiling channels having nonuniform axial heat flux profiles. The flow transient to be investigated consists of a step change in inlet flow rate. Since all flow transients may be decomposed into a finite number of steps, this incurs no loss in generality. Moreover, this transient permits a simple solution to be readily derived. To maintain tractability, only the case of no inlet subcooling is considered in this paper. Although this problem has been simplified, the results are useful for the assessment of computer codes used in the transient analysis of two-phase flow.
- OSTI ID:
- 6832001
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- Country of Publication:
- United States
- Language:
- English
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Study on critical heat flux in rectangular channels heated from one or both sides at pressures ranging from 0.1 to 14 MPa
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6885463
XITE--A DIGITAL PROGRAM FOR THE ANALYSIS OF TWO-DIMENSIONAL BOILING FLOW TRANSIENTS WITH FLUID EXPANSION
Technical Report
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Sun Mar 31 23:00:00 EST 1963
·
OSTI ID:4654277
Study on critical heat flux in rectangular channels heated from one or both sides at pressures ranging from 0.1 to 14 MPa
Journal Article
·
Thu Aug 01 00:00:00 EDT 1996
· Journal of Heat Transfer
·
OSTI ID:380765
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
TRANSIENTS
TWO-PHASE FLOW
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
TRANSIENTS
TWO-PHASE FLOW
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS