Effects of two maximas in axial heat flux on the stability of heated channels with two-phase flow
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6983586
- Univ. of Virginia, Charlottesville (United States)
The importance of density-wave-oscillation-induced instabilities in boiling water reactors (BWRs) has been recognized. Analysis of these instabilities in complex systems such as BWRs using computer codes based on numerical simulation of space-time thermal hydraulics or neutron kinetics coupled thermal hydraulics equations is time consuming. Hence, whenever possible, numerical simulation results must be supplemented with analytical frequency domain calculations and, if possible, with nonlinear analyses. Previous frequency domain stability analyses of density-wave oscillations were restricted to either uniformly heated channels or to heated channels with single-humped axially varying heat flux, such as represented by q[double prime](z) = q[double prime][sub o] sin (a + bz). Numerical simulations of BWR kinetics with thermalhydraulics feedback show that a double-humped axial power profile may result under certain conditions. To study the stability characteristics of heated channels with double-humped heat flux profiles, we have extended earlier frequency domain analysis of nonuniformly heated channels with two-phase flow.
- OSTI ID:
- 6983586
- Report Number(s):
- CONF-921102--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL CHANNELS
HEAT FLUX
HYDRAULICS
KINETICS
MATHEMATICAL MODELS
MECHANICS
OSCILLATIONS
POWER DISTRIBUTION
POWER REACTORS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR KINETICS
REACTOR STABILITY
REACTORS
STABILITY
THERMAL ANALYSIS
THERMAL REACTORS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL CHANNELS
HEAT FLUX
HYDRAULICS
KINETICS
MATHEMATICAL MODELS
MECHANICS
OSCILLATIONS
POWER DISTRIBUTION
POWER REACTORS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR KINETICS
REACTOR STABILITY
REACTORS
STABILITY
THERMAL ANALYSIS
THERMAL REACTORS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS