Analysis of the effect of spacer shape on coolant flow in a nuclear fuel assembly

Conference · Tue Dec 31 23:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7058225

Kanazawa, Toru; Nishida, Koji; Yokomizo, Osamu; Kawabe, Ryuhei ^[1]

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1. Energy Research Lab., Hitachi Ltd., Ibaraki (Japan)

The subchannel analysis code SILFEED has been developed to survey critical powers of a wide variety of boiling water reactor (BWR) fuel bundle designs. SILFEED is based on a film flow model, which calculates the process of liquid film flow depletion along the fuel rod surfaces. When the liquid film disappears, it is regarded as dryout. Fuel spacers affect bundle critical power. In SILFEED, the effect of spacers is assumed to depend only on their blockage ratio to the flow area. However, spacers have a three-dimensional shape, and certain shapes must give direction to the coolant flow. For example, a flow tab is considered to have such a function. Therefore, bundle critical power is influenced by spacer shape. In the present research, an analysis was carried out to examine the effect of three-dimensional spacer shape on coolant flow in a BWR fuel bundle. In particular, the effect of the flow tab on deposition characteristics of coolant droplets onto fuel rod surfaces was calculated by the three-dimensional flow analysis code. Then SILFEED was modified by incorporating the shape effect on droplet deposition characteristics.

• OSTI ID: 7058225
• Report Number(s): CONF-920606--
• Journal Information: Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 65; ISSN TANSA; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCURACY
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
DEPOSITION
DROPLETS
DRYOUT
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FILM FLOW
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FLUID-STRUCTURE INTERACTIONS
FUEL ASSEMBLIES
FUEL CHANNELS
HEAT TRANSFER
HYDRAULICS
IDEAL FLOW
MATHEMATICAL MODELS
MECHANICS
MONTE CARLO METHOD
PARTICLES
POWER REACTORS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
S CODES
SIMULATION
SPACERS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS