A preliminary computational fluid dynamics (CFD) analysis was performed to understand density-gradient-induced stratified flow in a Very High Temperature Reactor (VHTR) air-ingress accident. Various parameters were taken into consideration, including turbulence model, core temperature, initial air mole-fraction, and flow resistance in the core. The gas turbine modular helium reactor (GT-MHR) 600 MWt was selected as the reference reactor and it was simplified to be 2D geometry in modeling. The core and the lower plenum were assumed to be porous bodies. Following the preliminary CFD results, the analysis of the air-ingress accident has been performed by two different codes: GAMMA code (system analysis code, Oh et al. 2006) and FLUENT CFD code (Fluent 2007). Eventually, the analysis results showed that the actual onset time of natural convection (∼160 sec) would be significantly earlier than the previous predictions (∼150 hours) calculated based on the molecular diffusion air-ingress mechanism. This leads to the conclusion that the consequences of this accident will be much more serious than previously expected.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4351-2
PROCEEDINGS PAPER
Computational Fluid Dynamics Analyses on Very High Temperature Reactor Air Ingress
Chang H. Oh,
Chang H. Oh
Idaho National Laboratory, Idaho Falls, ID
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Eung S. Kim,
Eung S. Kim
Idaho National Laboratory, Idaho Falls, ID
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Richard Schultz,
Richard Schultz
Idaho National Laboratory, Idaho Falls, ID
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David Petti,
David Petti
Idaho National Laboratory, Idaho Falls, ID
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Hyung S. Kang
Hyung S. Kang
Korea Atomic Energy Research Institute, Daejeon, Korea
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Chang H. Oh
Idaho National Laboratory, Idaho Falls, ID
Eung S. Kim
Idaho National Laboratory, Idaho Falls, ID
Richard Schultz
Idaho National Laboratory, Idaho Falls, ID
David Petti
Idaho National Laboratory, Idaho Falls, ID
Hyung S. Kang
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
ICONE17-75863, pp. 943-949; 7 pages
Published Online:
February 25, 2010
Citation
Oh, CH, Kim, ES, Schultz, R, Petti, D, & Kang, HS. "Computational Fluid Dynamics Analyses on Very High Temperature Reactor Air Ingress." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 943-949. ASME. https://doi.org/10.1115/ICONE17-75863
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