Two design options of core distribution block (CDB) for a cooled-vessel design in the Very High Temperature Reactor (VHTR) were developed and the influence on the core hot spot was investigated by the commercial computational fluid dynamics (CFD) code, CFX-11. Isothermal CFD analyses were performed to estimate the coolant flow variation at the inlet of the coolant channel. The results predicted about 5% of the maximum velocity deviation when applying the core pressure drop of NHDD PMR200. A unit-cell CFD model was used to access the effect of the velocity deviation on the core hot spot. The unit-cell analyses were carried out for the velocity deviation of 0%, 5%, and 10%. Not only a constant power but also a local maximum power profile was considered. According to the results, the maximum fuel temperature was increased by about 30°C for the velocity deviation of 10% but still below the normal operation limit of 1250°C.
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ASME/JSME 2011 8th Thermal Engineering Joint Conference
March 13–17, 2011
Honolulu, Hawaii, USA
Conference Sponsors:
- Heat Transfer Division
ISBN:
978-0-7918-3892-1
PROCEEDINGS PAPER
CFD Analysis on the Influence of Coolant Distribution Blocks on the Core Hot Spot Temperature in a Prismatic Very High Temperature Reactor
Min-Hwan Kim,
Min-Hwan Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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Nam-il Tak,
Nam-il Tak
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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Jae Man Noh,
Jae Man Noh
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
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Goon-Cherl Park
Goon-Cherl Park
Seoul National University, Seoul, Republic of Korea
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Min-Hwan Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Nam-il Tak
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Jae Man Noh
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Goon-Cherl Park
Seoul National University, Seoul, Republic of Korea
Paper No:
AJTEC2011-44627, T20074; 5 pages
Published Online:
March 1, 2011
Citation
Kim, M, Tak, N, Noh, JM, & Park, G. "CFD Analysis on the Influence of Coolant Distribution Blocks on the Core Hot Spot Temperature in a Prismatic Very High Temperature Reactor." Proceedings of the ASME/JSME 2011 8th Thermal Engineering Joint Conference. ASME/JSME 2011 8th Thermal Engineering Joint Conference. Honolulu, Hawaii, USA. March 13–17, 2011. T20074. ASME. https://doi.org/10.1115/AJTEC2011-44627
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