Experimental study of laminar mixed convection in a rod bundle with mixing vane spacer grids

Lokanath Mohanta, Fan Bill Cheung, Stephen M. Bajorck, Kirk Tien, Chris L. Hoxie

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Abstract

Heat transfer by mixed convection in a rod bundle occurs when convection is affected by both the buoyancy and inertial forces. Mixed convection can be assumed when the Richardson number (Ri = Gr/Re2) is on the order of unity, indicating that both forced and natural convection are important contributors to heat transfer. In the present study, data obtained from the Rod Bundle Heat Transfer (RBHT) facility was used to determine the heat transfer coefficient in the mixed convection regime, which was found to be significantly larger than those expected assuming forced convection based on the inlet flow rate. The inlet Reynolds (Re) number in the tests ranged from 500 to 1300 while the Grashof (Gr) number varied from 1.5x 105 to 3.8x106 yielding 0.25 < Ri < 4.3. Using results from RBHT test along with the correlation from the FLECHT-SEASET test program for laminar forced convection, a new correlation for mixed convection in a rod bundle is proposed. The new correlation accounts for the enhancement of heat transfer relative to laminar forced convection.

Original languageEnglish (US)
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages5008-5019
Number of pages12
ISBN (Electronic)9781510811843
StatePublished - Jan 1 2015
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: Aug 30 2015Sep 4 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume6

Other

Other16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
CountryUnited States
CityChicago
Period8/30/159/4/15

Fingerprint

Mixed convection
vanes
spacers
forced convection
bundles
Forced convection
convection
rods
heat transfer
grids
Heat transfer
Grashof number
inlet flow
Richardson number
Inlet flow
heat transfer coefficients
Buoyancy
Natural convection
buoyancy
free convection

All Science Journal Classification (ASJC) codes

  • Instrumentation
  • Nuclear Energy and Engineering

Cite this

Mohanta, L., Cheung, F. B., Bajorck, S. M., Tien, K., & Hoxie, C. L. (2015). Experimental study of laminar mixed convection in a rod bundle with mixing vane spacer grids. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 (pp. 5008-5019). (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 6). American Nuclear Society.
Mohanta, Lokanath ; Cheung, Fan Bill ; Bajorck, Stephen M. ; Tien, Kirk ; Hoxie, Chris L. / Experimental study of laminar mixed convection in a rod bundle with mixing vane spacer grids. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 2015. pp. 5008-5019 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).
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Mohanta, L, Cheung, FB, Bajorck, SM, Tien, K & Hoxie, CL 2015, Experimental study of laminar mixed convection in a rod bundle with mixing vane spacer grids. in International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, vol. 6, American Nuclear Society, pp. 5008-5019, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, Chicago, United States, 8/30/15.

Experimental study of laminar mixed convection in a rod bundle with mixing vane spacer grids. / Mohanta, Lokanath; Cheung, Fan Bill; Bajorck, Stephen M.; Tien, Kirk; Hoxie, Chris L.

International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 2015. p. 5008-5019 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 6).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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AU - Cheung, Fan Bill

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AU - Tien, Kirk

AU - Hoxie, Chris L.

PY - 2015/1/1

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N2 - Heat transfer by mixed convection in a rod bundle occurs when convection is affected by both the buoyancy and inertial forces. Mixed convection can be assumed when the Richardson number (Ri = Gr/Re2) is on the order of unity, indicating that both forced and natural convection are important contributors to heat transfer. In the present study, data obtained from the Rod Bundle Heat Transfer (RBHT) facility was used to determine the heat transfer coefficient in the mixed convection regime, which was found to be significantly larger than those expected assuming forced convection based on the inlet flow rate. The inlet Reynolds (Re) number in the tests ranged from 500 to 1300 while the Grashof (Gr) number varied from 1.5x 105 to 3.8x106 yielding 0.25 < Ri < 4.3. Using results from RBHT test along with the correlation from the FLECHT-SEASET test program for laminar forced convection, a new correlation for mixed convection in a rod bundle is proposed. The new correlation accounts for the enhancement of heat transfer relative to laminar forced convection.

AB - Heat transfer by mixed convection in a rod bundle occurs when convection is affected by both the buoyancy and inertial forces. Mixed convection can be assumed when the Richardson number (Ri = Gr/Re2) is on the order of unity, indicating that both forced and natural convection are important contributors to heat transfer. In the present study, data obtained from the Rod Bundle Heat Transfer (RBHT) facility was used to determine the heat transfer coefficient in the mixed convection regime, which was found to be significantly larger than those expected assuming forced convection based on the inlet flow rate. The inlet Reynolds (Re) number in the tests ranged from 500 to 1300 while the Grashof (Gr) number varied from 1.5x 105 to 3.8x106 yielding 0.25 < Ri < 4.3. Using results from RBHT test along with the correlation from the FLECHT-SEASET test program for laminar forced convection, a new correlation for mixed convection in a rod bundle is proposed. The new correlation accounts for the enhancement of heat transfer relative to laminar forced convection.

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M3 - Conference contribution

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Mohanta L, Cheung FB, Bajorck SM, Tien K, Hoxie CL. Experimental study of laminar mixed convection in a rod bundle with mixing vane spacer grids. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society. 2015. p. 5008-5019. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).