This CFD study is to simulate a coolant (gas) flow and heat transfer in a PBR core during a normal operation. This study used a pebble array with direct area contacts among the pebbles which is one of the pebbles arrangements for a detailed simulation of PBR core CFD studies. A CFD model is developed to more adequately represent the pebbles randomly stacked in the PBR core. The CFD predictions showed a large variation of the temperature on the pebble surface as well as in the pebble core. The temperature drop in the outer graphite layer is smaller than that in the pebble-core region. This is because the thermal conductivity of graphite is higher than the fuel (UO2 mixture) conductivity in the pebble core. Higher pebble surface temperature is predicted downstream of the pebble contact due to a reverse flow. Multiple vortices are predicted to occur downstream of the spherical pebbles due to a flow separation. The coolant flow structure and fuel temperature in the PBR core appears to largely depend on the in-core distribution of the pebbles.
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Fourth International Topical Meeting on High Temperature Reactor Technology
September 28–October 1, 2008
Washington, DC, USA
Conference Sponsors:
- ASME
ISBN:
978-0-7918-4854-8
PROCEEDINGS PAPER
CFD Simulation of a Coolant Flow and a Heat Transfer in a Pebble Bed Reactor
Wang-Kee In,
Wang-Kee In
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Won-Jae Lee,
Won-Jae Lee
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Yassin A. Hassan
Yassin A. Hassan
Texas A&M University, College Station, TX
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Wang-Kee In
Korea Atomic Energy Research Institute, Daejeon, South Korea
Won-Jae Lee
Korea Atomic Energy Research Institute, Daejeon, South Korea
Yassin A. Hassan
Texas A&M University, College Station, TX
Paper No:
HTR2008-58334, pp. 171-175; 5 pages
Published Online:
July 1, 2009
Citation
In, W, Lee, W, & Hassan, YA. "CFD Simulation of a Coolant Flow and a Heat Transfer in a Pebble Bed Reactor." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1. Washington, DC, USA. September 28–October 1, 2008. pp. 171-175. ASME. https://doi.org/10.1115/HTR2008-58334
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