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

Technical Report · Sat Apr 01 04:00:00 EST 1978

OSTI ID:5562702

Chiu, C; Todreas, N; Rohsenow, W

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. The constants in this model for each type of subchannel were determined using all experimental data in the literature and the results of two tests performed as part of this study to fill a gap in the available literature. These experiments to measure flow split were performed on two wire-wrapped 61 pin bundles of pin pitch to pin diameter ratio, P/D, equal to 1.063 and wire lead to pin diameter ratios, H/D, of 4 and 8. The predictions of this model match all experimental data in the literature within +- 5%.

• Research Organization: Massachusetts Inst. of Tech., Cambridge (USA). Dept. of Nuclear Engineering
• DOE Contract Number: AS02-76ET37240
• OSTI ID: 5562702
• Report Number(s): DOE/ET/37240-T3-Rev.1; COO-2245-56TR-Rev.1; ON: DE82007742
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
REACTOR COMPONENTS
REACTORS
TURBULENT FLOW