Assessment of the local hot core temperature during normal operation in a pebble-bed type very high temperature reactor has been carried out by using the computational fluid dynamic (CFD) method for which the boundary conditions were obtained from the results of a macroscopic analysis of the core using a system thermal analysis code, GAMMA. Three pebble arrangements are selected, which are simple cubic (SC), body-centered cubic, and face-centered cubic. The results showed that the SC arrangement having the lowest porosity gives the highest fuel temperature of but still below the normal operational fuel limit of . Comparison of the CFD results with an empirical correlation was made for the pressure drop and Nusselt number. Both results showed a similar tendency that the pressure drop and the Nusselt number increases as the porosity decreases but there were large differences in their absolute values. The benchmark calculation for the pressure drop of the packed particles in a square channel indicated that the correlation for the full core used in the system code is not appropriate for the prediction of a local thermal-fluid behavior in an ordered pebble arrangement.
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e-mail: mhkim@kaeri.re.kr
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January 2009
Research Papers
Computational Fluid Dynamics Assessment of the Local Hot Core Temperature in a Pebble-Bed Type Very High Temperature Reactor
Min-Hwan Kim,
e-mail: mhkim@kaeri.re.kr
Min-Hwan Kim
Korea Atomic Energy Research Institute
, 1045 Daedeokdaero, Yoseong, Daejeon, 304-353, Republic of Korea
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Hong-Sik Lim,
Hong-Sik Lim
Korea Atomic Energy Research Institute
, 1045 Daedeokdaero, Yoseong, Daejeon, 304-353, Republic of Korea
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Won Jae Lee
Won Jae Lee
Korea Atomic Energy Research Institute
, 1045 Daedeokdaero, Yoseong, Daejeon, 304-353, Republic of Korea
Search for other works by this author on:
Min-Hwan Kim
Korea Atomic Energy Research Institute
, 1045 Daedeokdaero, Yoseong, Daejeon, 304-353, Republic of Koreae-mail: mhkim@kaeri.re.kr
Hong-Sik Lim
Korea Atomic Energy Research Institute
, 1045 Daedeokdaero, Yoseong, Daejeon, 304-353, Republic of Korea
Won Jae Lee
Korea Atomic Energy Research Institute
, 1045 Daedeokdaero, Yoseong, Daejeon, 304-353, Republic of KoreaJ. Eng. Gas Turbines Power. Jan 2009, 131(1): 012905 (6 pages)
Published Online: October 2, 2008
Article history
Received:
July 21, 2008
Revised:
July 28, 2008
Published:
October 2, 2008
Citation
Kim, M., Lim, H., and Lee, W. J. (October 2, 2008). "Computational Fluid Dynamics Assessment of the Local Hot Core Temperature in a Pebble-Bed Type Very High Temperature Reactor." ASME. J. Eng. Gas Turbines Power. January 2009; 131(1): 012905. https://doi.org/10.1115/1.2983136
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