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Turbulent flow split model and supporting experiments for wire-wrapped core assemblies. [LMFBR]

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5138324
; ;
A flow split model for the turbulent flow in a wire-wrapped nuclear fuel rod assembly is developed taking the form drag and sweeping flow between subchannels into consideration. This model is applicable to the flow distribution between two types of subchannels, i.e., interior and edge subchannels. 16 refs.
Research Organization:
MIT, Cambridge, Mass
OSTI ID:
5138324
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 50:1; ISSN NUTYB
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
REACTOR COMPONENTS
REACTORS
TURBULENT FLOW
WIRES