Subchannel analysis program for boiling water reactor fuel bundles based on five conservation equations of two-phase flow
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6222968
A subchannel analysis program, MENUETT, is developed for evaluation of thermal-hydraulic characteristics in boiling water reactor fuel bundles. This program is based on five conservation equations of two-phase flow with the drift-flux correlation. The cross flows are calculated separately for liquid and vapor phases from the lateral momentum conservation equation. The effects of turbulent mixing and void drift are accounted for in the program. The conservation equations are implicitly differentiated with the convective terms by the donor-cell method, and are solved iteratively in the axial and lateral directions. Data of the 3 X 3 rod bundle experiments are used for program verification. The lateral distributions of equilibrium quality and mass flow rate at the bundle exit calculated by the program compare satisfactorily with the experimental results.
- Research Organization:
- Energy Research Laboratory, Hitachi, Ltd., Hitachi-shi, Ibaraki-ken
- OSTI ID:
- 6222968
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 69:2; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Sensitivity Studies of the Inter-subchannel Mixing in Subchannel Analysis
Subchannel analysis applied to neutron noise investigation in a boiling water reactor
Analysis of two-phase flow inter-subchannel mass and momentum exchanges by the two-fluid model approach
Journal Article
·
Sat Jul 01 00:00:00 EDT 2017
· Transactions of the American Nuclear Society
·
OSTI ID:23050396
Subchannel analysis applied to neutron noise investigation in a boiling water reactor
Thesis/Dissertation
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:6683484
Analysis of two-phase flow inter-subchannel mass and momentum exchanges by the two-fluid model approach
Conference
·
Fri Sep 01 00:00:00 EDT 1995
·
OSTI ID:111427
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FUEL CHANNELS
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
HYDRAULICS
ITERATIVE METHODS
M CODES
MATHEMATICAL MODELS
MECHANICS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
ROD BUNDLES
SIMULATION
TURBULENCE
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FUEL CHANNELS
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
HYDRAULICS
ITERATIVE METHODS
M CODES
MATHEMATICAL MODELS
MECHANICS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
ROD BUNDLES
SIMULATION
TURBULENCE
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS