The nuclear core of High Temperature Gas Reactor (HTGR) with pebble bed type has been investigated intensively due to its benefits in management, but its complicated flow geometry requested the reliable analytical method. Recent studies have been made using the three dimensional computational methods but they need to be evaluated with the experimental data. Due to the complicated and narrow flow channel, the intrusive methods of flow measurement are not proper in the study. In the present study, we developed a wind tunnel for the pebble bed geometry in the structure of Face Centered Cubic (FCC) and measure the flow field using the Particle Image Velocimetry (PIV) directly. Due to the limitation of the image harnessing speed and accessibility of the light for particle identification, the system is scaled up to reduce the mean flow velocity by keeping the same Reynolds number of the HTGR. The velocity fields are successfully determined to identify the stagnation points suspected to produce hot spots on the surface of the pebble. It is expected that the present data is useful to evaluate the three dimensional Computational Fluid Dynamics (CFD) analysis. Furthermore, It would provide an insight of experimental method if the present results are compared by those of scaled down and liquid medium.
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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:
978-0-7918-4855-5
PROCEEDINGS PAPER
Flow Visualization of Pebble Bed HTGR
Jae-Young Lee,
Jae-Young Lee
Han Dong Global University, Pohang, Gyeongbuk, South Korea
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Sa-Ya Lee
Sa-Ya Lee
Han Dong Global University, Pohang, Gyeongbuk, South Korea
Search for other works by this author on:
Jae-Young Lee
Han Dong Global University, Pohang, Gyeongbuk, South Korea
Sa-Ya Lee
Han Dong Global University, Pohang, Gyeongbuk, South Korea
Paper No:
HTR2008-58063, pp. 319-322; 4 pages
Published Online:
July 1, 2009
Citation
Lee, J, & Lee, S. "Flow Visualization of Pebble Bed HTGR." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2. Washington, DC, USA. September 28–October 1, 2008. pp. 319-322. ASME. https://doi.org/10.1115/HTR2008-58063
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