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

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

Nuclear Energy and Fuel Cycle Division

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

10 Scopus citations

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.

Original language	English
Title of host publication	International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Publisher	American Nuclear Society
Pages	979-995
Number of pages	17
ISBN (Electronic)	9781510811843
State	Published - 2015
Event	16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States Duration: Aug 30 2015 → Sep 4 2015

Publication series

Name	International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume	2

Conference

Conference	16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Country/Territory	United States
City	Chicago
Period	08/30/15 → 09/4/15

Funding

ACKNOWLEDGMENTS The authors acknowledge the financial support provided by the U.S. Department of Energy project number (NEUP 13-4953 (DE-NE0000744)) for the 4th generation nuclear energy, which made this work possible.

Keywords

CFD
Missouri S & T
Natural circulation
OSU-HTTF
VHTR

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 (pp. 979-995). (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 2). American Nuclear Society.

Kao, M. T. ; Jain, P. ; Usman, S. 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. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 2015. pp. 979-995 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).

@inproceedings{21a3c9a8a2f1430b8dc202fe46981f36,

title = "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",

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.",

keywords = "CFD, Missouri S & T, Natural circulation, OSU-HTTF, VHTR",

author = "Kao, {M. T.} and P. Jain and S. Usman and Said, {I. A.} and Taha, {M. M.} and Al-Dahhan, {M. H.} and Rizwan-Uddin",

note = "Publisher Copyright: {\textcopyright} Copyright (2015) by American Nuclear Society All rights reserved.; 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 ; Conference date: 30-08-2015 Through 04-09-2015",

year = "2015",

language = "English",

series = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",

publisher = "American Nuclear Society",

pages = "979--995",

booktitle = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",

}

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. 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, 08/30/15.

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

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - 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

AU - Kao, M. T.

AU - Jain, P.

AU - Usman, S.

AU - Said, I. A.

AU - Taha, M. M.

AU - Al-Dahhan, M. H.

AU - Rizwan-Uddin,

PY - 2015

Y1 - 2015

N2 - 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.

AB - 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.

KW - CFD

KW - Missouri S & T

KW - Natural circulation

KW - OSU-HTTF

KW - VHTR

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M3 - Conference contribution

AN - SCOPUS:84962684160

T3 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015

SP - 979

EP - 995

BT - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015

PB - American Nuclear Society

T2 - 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015

Y2 - 30 August 2015 through 4 September 2015

ER -

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

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