Subchannel void fraction prediction via drift-flux analysis

Journal Article · Wed Oct 01 00:00:00 EDT 1986 · Nucl. Technol.; (United States)

OSTI ID:6952457

Khan, H J; Kosaly, G

Void fraction calculations have been performed using the subchannel drift-flux code CANAL. Using void and flow distributions in rod bundle geometry, a value of C/sub 0/ has been estimated for bundle-averaged void fraction calculation in one-dimensional approximations. Successful prediction of the average void fraction is observed for the annular rod bundle geometry of the FRIGG experiment. In order to perform subchannel void fraction calculation, a C/sub 0/ model has been developed for one-dimensional subchannel geometry. The implicit form of the C/sub 0/ model developed accounts for void and flow conditions in the adjacent subchannels existing at the common interfaces, i.e., at the gap spacing between the subchannels. It appears that the magnitude of C/sub 0/ varies between subchannels (annular rings of FRIGG geometry) but remains almost constant within each subchannel. Good agreement is observed between prediction and data for subchannel void fractions in axially uniform and nonuniform heated rod bundles.

• Research Organization: Univ. of Washington, Dept. of Nuclear Engineering, BF-10, Seattle, WA 98195
• OSTI ID: 6952457
• Journal Information: Nucl. Technol.; (United States), Vol. 75:1
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
ROD BUNDLES
C CODES
VOID FRACTION
COMPUTERIZED SIMULATION
DATA ANALYSIS
F CODES
FLOW MODELS
GEOMETRY
HEATING
ONE-DIMENSIONAL CALCULATIONS
RESEARCH PROGRAMS
COMPUTER CODES
MATHEMATICAL MODELS
MATHEMATICS
SIMULATION
220300* - Nuclear Reactor Technology- Fuel Elements