Generalized theory for predicting mass effluence during reactor reflooding
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6240568
A simple generalized model has been developed to predict the rate of mass effluence during bottom reflooding, which is an emergency core cooling mechanism for the light water reactors. The effluence of mass during reflooding is important not only for determining the core heat transfer rate, but also the overall system pressure drop characteristics. The model accounts for the propagation of the quench front and vaporization below the quench front. It treats the quench front explicitly as a reference for mass and energy balance considerations. Comparisons were made between the model predictions and full-length bundle data with two power profiles and basic single-tube data. The results demonstrate that the rate of mass effluence is strongly coupled to the rate of quench front propagation in the core.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA
- OSTI ID:
- 6240568
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 43:1; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Predictions of FLECHT bottom reflood experiments using RELAP5/MOD2
Reflood heat transfer correlation
Transient non-equilibrium two-phase flow: reflooding of a vertical flow channel
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6883189
Reflood heat transfer correlation
Journal Article
·
Fri Nov 30 23:00:00 EST 1979
· Nucl. Technol.; (United States)
·
OSTI ID:5533003
Transient non-equilibrium two-phase flow: reflooding of a vertical flow channel
Thesis/Dissertation
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:5045427
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CORE FLOODING SYSTEMS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
HEAT TRANSFER
HYDRODYNAMICS
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
PRESSURE DROP
PWR TYPE REACTORS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CORE FLOODING SYSTEMS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
HEAT TRANSFER
HYDRODYNAMICS
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
PRESSURE DROP
PWR TYPE REACTORS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS