Two-fluid modeling of two-phase flow in BWR cores
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5165587
None
- Research Organization:
- Sandia, Albuquerque, NM 87185
- OSTI ID:
- 5165587
- Report Number(s):
- CONF-810606-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 38
- Country of Publication:
- United States
- Language:
- English
Similar Records
Two-fluid modeling of two-phase flow in BWR cores
Analytical modeling of transient two-phase flow. [PWR; BWR]
Theoretical foundation for the modeling of two-phase flow. [PWR; BWR]
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:6475372
Analytical modeling of transient two-phase flow. [PWR; BWR]
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5686928
Theoretical foundation for the modeling of two-phase flow. [PWR; BWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6594791
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
EQUATIONS
EQUATIONS OF STATE
FINITE DIFFERENCE METHOD
FLUID FLOW
ITERATIVE METHODS
MATHEMATICAL MODELS
NUMERICAL SOLUTION
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
STABILITY
STEADY-STATE CONDITIONS
TRANSIENTS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
EQUATIONS
EQUATIONS OF STATE
FINITE DIFFERENCE METHOD
FLUID FLOW
ITERATIVE METHODS
MATHEMATICAL MODELS
NUMERICAL SOLUTION
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
STABILITY
STEADY-STATE CONDITIONS
TRANSIENTS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS