Flow visualization of pebble bed HTGR

Jae Young Lee, Sa Ya Lee

Research output: Chapter in Book/Report/Conference proceedingConference contribution

14 Scopus citations

Abstract

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.

Original languageEnglish (US)
Title of host publication2008 Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology, HTR 2008
Pages319-322
Number of pages4
StatePublished - 2009
Event2008 4th International Topical Meeting on High Temperature Reactor Technology, HTR 2008 - Washington, DC, United States
Duration: Sep 28 2008Oct 1 2008

Publication series

Name2008 Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology, HTR 2008
Volume2

Conference

Conference2008 4th International Topical Meeting on High Temperature Reactor Technology, HTR 2008
Country/TerritoryUnited States
CityWashington, DC
Period9/28/0810/1/08

All Science Journal Classification (ASJC) codes

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering

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