A distribution parameter derived for rectangular channels and simulated subchannel geometry
Journal Article
·
· Nuclear Technology; (USA)
OSTI ID:6772572
- Maryland Univ., College Park, MD (USA). Dept. of Mechanical Engineering
The distribution parameter of the drift-flux model has been developed for a rectangular channel and a simulated boiling water reactor (BWR) subchannel. The void fraction prediction by the subchannel drift-flux code CANAL is demonstrated for heated rectangular channels. Intrasubchannel flow and void profiles are considered for subchannel model development. Distribution parameter C{sub 0} is found to be very sensitive to variation of the geometric parameters and subchannel types. Since void fraction measurements corresponding to the rectangular subchannel of a BWR rod bundle are unavailable at present, assessment of the derived models remains to be performed.
- OSTI ID:
- 6772572
- Journal Information:
- Nuclear Technology; (USA), Journal Name: Nuclear Technology; (USA) Vol. 90:2; ISSN NUTYB; ISSN 0029-5450
- 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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
220400* -- Nuclear Reactor Technology-- Control Systems
BWR TYPE REACTORS
C CODES
COMPUTER CODES
DESIGN
GEOMETRY
MATHEMATICS
PARAMETRIC ANALYSIS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
ROD BUNDLES
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
220400* -- Nuclear Reactor Technology-- Control Systems
BWR TYPE REACTORS
C CODES
COMPUTER CODES
DESIGN
GEOMETRY
MATHEMATICS
PARAMETRIC ANALYSIS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
ROD BUNDLES
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS