Void fraction of nonequilibrium two-phase flow in rod bundles
Journal Article
·
· Heat Transfer - Soviet Research; (USA)
OSTI ID:5773001
- Polzunov Boiler and Turbine Inst., Leningrad (SU)
A method for calculating the void fractions in rod bundles with thermohydraulically nonequivalent flow cells is presented. Satisfactory agreement between the predicted values and published experimental data is obtained.
- OSTI ID:
- 5773001
- Journal Information:
- Heat Transfer - Soviet Research; (USA), Journal Name: Heat Transfer - Soviet Research; (USA) Vol. 21:6; ISSN 0440-5749; ISSN HTSRA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Void fraction prediction in two-phase flow across a tube bundle
Void fraction distribution in a heated rod bundle under flow stagnation conditions
The void fraction in bundles of circular fuel rods generating steam in nuclear reactors
Journal Article
·
Tue Mar 31 23:00:00 EST 1992
· AIChE Journal (American Institute of Chemical Engineers); (United States)
·
OSTI ID:5257355
Void fraction distribution in a heated rod bundle under flow stagnation conditions
Conference
·
Fri Sep 01 00:00:00 EDT 1995
·
OSTI ID:111429
The void fraction in bundles of circular fuel rods generating steam in nuclear reactors
Journal Article
·
Tue Oct 31 23:00:00 EST 1989
· Heat Transfer - Soviet Research; (USA)
·
OSTI ID:5787749
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
42 ENGINEERING
420400* -- Engineering-- Heat Transfer & Fluid Flow
CALCULATION METHODS
CORRELATIONS
DATA
EXPERIMENTAL DATA
FLUID FLOW
FUEL ELEMENTS
FUEL RODS
INFORMATION
NUMERICAL DATA
REACTOR COMPONENTS
ROD BUNDLES
TWO-PHASE FLOW
VOID FRACTION
220300 -- Nuclear Reactor Technology-- Fuel Elements
42 ENGINEERING
420400* -- Engineering-- Heat Transfer & Fluid Flow
CALCULATION METHODS
CORRELATIONS
DATA
EXPERIMENTAL DATA
FLUID FLOW
FUEL ELEMENTS
FUEL RODS
INFORMATION
NUMERICAL DATA
REACTOR COMPONENTS
ROD BUNDLES
TWO-PHASE FLOW
VOID FRACTION