@inproceedings{b01a622797e1481e84fa8398cf67ac7c,
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 = "Funding Information: 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. 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 (US)",
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",
}