Investigation of plenum-to-plenum heat transfer and gas dynamics under natural circulation in a scaled-down dual channel module mimicking prismatic VHTR core using CFD

M. T. Kao, P. Jain, S. Usman, I. A. Said, M. M. Taha, M. H. Al-Dahhan, Rizwan-Uddin

Research output: ResearchConference contribution

Abstract

In this study, two CFD packages, STAR-CCM+ and COMSOL were used to simulate scaled experimental facilities mimicking a dual channel natural circulation behavior in VHTR's and mimicking prismatic VHTR core and plena operation under natural circulation conditions to simulate the natural flow conditions in P2P, identify stream line, and velocity variations in the upper plenum and the two channels at given initial conditions for two different cases of 0.8 MPa and 4.2 MPa. A dual channel module represents a scaled down prismatic block reactor mimicking OSU-HTTF with a scaling down ratio of 1/4 axially and 1/4 radially with a diameter similar to OSU-HTTF cooler channel (0.625 inch) and length of channel is identical to 1/4 to the length of channels of OSU-HTTF of reactor core diameter 1 foot with reference OSU-HTTF. Dual-channel module was meshed with 1 million cells for the two cases. Simulations were carried out for Helium at pressure values of 0.8 MPa and 4.2 MPa.

LanguageEnglish (US)
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages979-995
Number of pages17
Volume2
ISBN (Electronic)9781510811843
StatePublished - 2015
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: Aug 30 2015Sep 4 2015

Other

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

Fingerprint

gas dynamics
charge flow devices
modules
heat transfer
Reactor cores
Gas dynamics
Helium
Computational fluid dynamics
Heat transfer
reactor cores
coolers
helium
reactors
scaling
cells
simulation

Keywords

  • CFD
  • Missouri S & T
  • Natural circulation
  • OSU-HTTF
  • VHTR

ASJC Scopus subject areas

  • Instrumentation
  • Nuclear Energy and Engineering

Cite this

Kao, M. T., Jain, P., Usman, S., Said, I. A., Taha, M. M., Al-Dahhan, M. H., & Rizwan-Uddin (2015). Investigation of plenum-to-plenum heat transfer and gas dynamics under natural circulation in a scaled-down dual channel module mimicking prismatic VHTR core using CFD. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 (Vol. 2, pp. 979-995). American Nuclear Society.

Investigation of plenum-to-plenum heat transfer and gas dynamics under natural circulation in a scaled-down dual channel module mimicking prismatic VHTR core using CFD. / Kao, M. T.; Jain, P.; Usman, S.; Said, I. A.; Taha, M. M.; Al-Dahhan, M. H.; Rizwan-Uddin.

International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. Vol. 2 American Nuclear Society, 2015. p. 979-995.

Research output: ResearchConference contribution

Kao, MT, Jain, P, Usman, S, Said, IA, Taha, MM, Al-Dahhan, MH & Rizwan-Uddin 2015, Investigation of plenum-to-plenum heat transfer and gas dynamics under natural circulation in a scaled-down dual channel module mimicking prismatic VHTR core using CFD. in International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. vol. 2, American Nuclear Society, pp. 979-995, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, Chicago, United States, 8/30/15.
Kao MT, Jain P, Usman S, Said IA, Taha MM, Al-Dahhan MH et al. Investigation of plenum-to-plenum heat transfer and gas dynamics under natural circulation in a scaled-down dual channel module mimicking prismatic VHTR core using CFD. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. Vol. 2. American Nuclear Society. 2015. p. 979-995.
Kao, M. T. ; Jain, P. ; Usman, S. ; Said, I. A. ; Taha, M. M. ; Al-Dahhan, M. H. ; Rizwan-Uddin. / Investigation of plenum-to-plenum heat transfer and gas dynamics under natural circulation in a scaled-down dual channel module mimicking prismatic VHTR core using CFD. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. Vol. 2 American Nuclear Society, 2015. pp. 979-995
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AU - Said,I. A.

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