NDLI: The Effect of Support Grid Design on Azimuthal Variations in Heat Transfer Coefficient for Rod Bundles

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Mary, V. Holloway Timothy, A. Conover Heather, L. Mccluskey Donald, E. Beasley Michael, E. Conner
Copyright Year	2003
Abstract	Support grids are an integral part of nuclear reactor fuel bundle design. Features, such as vane pairs, are placed on the downstream edge of support grids to enhance heat transfer and delay departure from nucleate boiling. The complex flow fields created by these features cause spatially varying heat transfer conditions on the surfaces of the rods. Azimuthal variations in heat transfer for a standard grid, split-vane pair grid, and disc grid are measured in the present study using a heated, thin film sensor. Normalized values of the variations in Nusselt number are presented for the support grid designs at axial locations ranging from 2.2 to 36.7 Dh. Two Reynolds numbers, Re = 28,000 and Re = 42,000 are tested. Results identify distinctive azimuthal variations in Nusselt number for all three of the support grid designs tested. The split-vane pair grid exhibits the largest variations in azimuthal heat transfer while the disc grid has the most uniform heat transfer.
Sponsorship	Heat Transfer Division
Starting Page	289
Ending Page	296
Page Count	8
File Format	PDF
ISBN	0791837181
DOI	10.1115/IMECE2003-41939
Volume Number	Heat Transfer, Volume 4
Conference Proceedings	ASME 2003 International Mechanical Engineering Congress and Exposition
Language	English
Publisher Date	2003-11-15
Publisher Place	Washington, DC, USA
Access Restriction	Subscribed
Subject Keyword	Design Nuclear fuels Reynolds number Disks Nucleate boiling Rods Thin film sensors Delays Heat transfer coefficients Flow (dynamics) Heat transfer Fuel rods
Content Type	Text
Resource Type	Article

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The Effect of Support Grid Design on Azimuthal Variation in Heat Transfer Coefficient for Rod Bundles

The Effect of Support Grid Features on Local, Single-Phase Heat Transfer Measurements in Rod Bundles

Development of a Convective Heat Transfer Measurement Technique for Flow Downstream of Support Grids in Rod Bundles

Subcooled Boiling Data From Rod Bundles

The Spacer Grid Effect on Heat Transfer at Low Flow Rate in a 5×5 Rod Bundles

Extending the Applicability of the Flow Boiling Correlation to Low Reynolds Number Flows in Microchannels

CFD Modeling of Fuel Rod Heat Transfer to Aid in the Risk Assessment of Fuel Rod Failure Due to Localized Crud

Departure From Nucleate Boiling Modeling Development for PWR Fuel

Analyses of Single-Phase Heat Transfer and Onset of Nucleate Boiling in Rod Bundles

The Effect of Support Grid Design on Azimuthal Variations in Heat Transfer Coefficient for Rod Bundles

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The Effect of Support Grid Design on Azimuthal Variation in Heat Transfer Coefficient for Rod Bundles

The Effect of Support Grid Features on Local, Single-Phase Heat Transfer Measurements in Rod Bundles

Development of a Convective Heat Transfer Measurement Technique for Flow Downstream of Support Grids in Rod Bundles

Subcooled Boiling Data From Rod Bundles

The Spacer Grid Effect on Heat Transfer at Low Flow Rate in a 5×5 Rod Bundles

Extending the Applicability of the Flow Boiling Correlation to Low Reynolds Number Flows in Microchannels

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