Numerical calculation of flashing from long pipes using a two-field model
Technical Report
·
OSTI ID:7186226
A two-field model for two-phase flows, in which the vapor and liquid phases have different densities, velocities, and temperatures, has been used to calculate the flashing of water from long pipes. The IMF (implicit Multifield) technique is used to numerically solve the transient equations that govern the dynamics of each phase. The flow physics is described with finite rate phase transitions, interfacial friction, heat transfer, pipe wall friction, and appropriate state equations. The results of the calculations are compared with measured histories of pressure, temperature, and void fraction. A parameter study indicates the relative sensitivity of the results to the various physical models that are used.
- Research Organization:
- Los Alamos Scientific Lab., N.Mex. (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 7186226
- Report Number(s):
- LAMS-NUREG-6330
- 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
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
EVAPORATION
FAILURES
FLASHING
FLUID FLOW
MATHEMATICAL MODELS
PHASE TRANSFORMATIONS
PIPES
PRESSURE RELEASE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
EVAPORATION
FAILURES
FLASHING
FLUID FLOW
MATHEMATICAL MODELS
PHASE TRANSFORMATIONS
PIPES
PRESSURE RELEASE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS