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Research Papers

Experimental Heat Transfer in an Annular Channel and 3-Rod Bundle Cooled With Upward Flow of Supercritical Water

[+] Author and Article Information
V. G. Razumovskiy

Thermal Power Engineering Department,
National Technical University of Ukraine, Kiev Polytechnic Institute,
37 Prospect Peremogy,
Kyiv 03056, Ukraine
e-mail: vgrazum@yandex.ru

Eu. N. Pis’mennyi

Thermal Power Engineering Department,
National Technical University of Ukraine Kiev Polytechnic Institute,
37 Prospect Peremogy,
Kyiv 03056, Ukraine
e-mail: evgnik@i.com.ua

Kh. Sidawi

Faculty of Energy Systems and Nuclear Sciences, University of Ontario Institute of Technology,
2000 Simcoe Street North,
Oshawa, ON L1H 7K4, Canada
e-mail: khalil.sidawi@uoit.net

I. L. Pioro

Faculty of Energy Systems and Nuclear Sciences, University of Ontario Institute of Technology,
2000 Simcoe Street North,
Oshawa, ON L1H 7K4, Canada
e-mail: igor.pioro@uoit.ca

A. Eu. Koloskov

Thermal Power Engineering Department,
National Technical University of Ukraine, Kiev Polytechnic Institute,
37 Prospect Peremogy,
Kyiv 03056, Ukraine
e-mail: aek_@i.ua

Manuscript received June 23, 2015; final manuscript received October 5, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.

ASME J of Nuclear Rad Sci 2(1), 011010 (Dec 09, 2015) (8 pages) Paper No: NERS-15-1117; doi: 10.1115/1.4031818 History: Received June 23, 2015

There have been relatively few publications detailing heat transfer to supercritical water (SCW) flowing through a channel with a bundle or just with a single rod (annular channel) as compared to heat transfer to SCW in bare tubes. In the present paper, results of experimental heat transfer to SCW flowing upward in an annular channel with a heated rod equipped with four helical ribs and a 3-rod bundle (rods are also equipped with four helical ribs) are discussed. The experimental results include bulk-fluid-temperature, wall-temperature, and heat-transfer-coefficient (HTC) profiles along the heated length (485 mm) for these flow geometries. Data obtained from this study could be applicable as a reference estimation of heat transfer for future fuel-bundle designs.

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Figures

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Fig. 6

Radial cross sections of annular channel and 3-rod bundle (Note: a Ukrainian SS has been used, but by content and other parameters, this steel is very close to SS-304)

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Fig. 5

3-D image of heated 3-rod bundle channel

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Fig. 4

3-D image of heated central rod annular channel

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Fig. 3

General schematic of SCW experimental setup

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Fig. 2

T–s diagram of water

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Fig. 1

P−T diagram of water

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Fig. 7

Variation of electrical resistivity for SS-304 along the heated length

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Fig. 8

Bulk-fluid-temperature, wall-temperature, and HTC profiles along heated length of annular channel: symbols: experimental data; lines: calculated profiles; heat flux: 1.543  MW/m2

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Fig. 9

Bulk-fluid-temperature, wall-temperature, and HTC profiles along heated length of annular channel: symbols: experimental data; lines: calculated profiles; heat flux: 1.758  MW/m2

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Fig. 10

Bulk-fluid-temperature, wall-temperature, and HTC profiles along heated length of annular channel: symbols: experimental data; lines: calculated profiles; heat flux: 2.033  MW/m2

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Fig. 11

Bulk-fluid-temperature, wall-temperature, and HTC profiles along heated length of annular channel: symbols: experimental data; lines: calculated profiles; heat flux: 2.244  MW/m2

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Fig. 12

Bulk-fluid-temperature, wall-temperature, and HTC profiles along heated length of annular channel: symbols: experimental data; lines: calculated profiles; heat flux: 2.547  MW/m2

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Fig. 13

Bulk-fluid-temperature, wall-temperature, and HTC profiles along heated length of 3-rod bundle: symbols: experimental data; lines: calculated profiles; heat flux: 3.2  MW/m2

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Fig. 14

Bulk-fluid-temperature, wall-temperature, and HTC profiles along heated length of 3-rod bundle: symbols: experimental data; lines: calculated profiles; heat flux: 3.07  MW/m2; inlet temperature: 166°C

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Fig. 15

Bulk-fluid-temperature, wall-temperature, and HTC profiles along heated length of 3-rod bundle: symbols: experimental data; lines: calculated profiles; heat flux: 3.07  MW/m2; inlet temperature: 212°C

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