Spent nuclear fuel generated at nuclear power plants must be safely stored during interim storage periods. A concrete storage cask developed for this purpose should be able to adequately emit the decay heat from the spent nuclear fuel. Moreover, the concrete storage cask must ensure that the temperatures of the spent nuclear fuel assemblies are maintained within the allowable values under normal and offnormal conditions and during an accident. However, the thermal conductivity of concrete is low and the allowable temperature of concrete is lower than that of steel. Therefore, the concrete storage cask must be designed to have heat removal capabilities with appropriate reliability. Accordingly, a passive heat removal system was designed to maintain the temperatures of the fuel assembly cladding material and concrete storage cask components within the allowable limits. The passive heat removal system consists of four air inlets and four air outlets with openings that are covered by mesh screens to prevent debris or wildlife from entering the ventilation ducts. The effect of each screen on the heat removal of the concrete storage cask depends on its mesh size. Therefore, thermal tests were performed to evaluate the heat removal performance in accordance with the mesh size of the screen. The screen mesh size was estimated to have an insignificant effect on the temperature rise of the canister surface and the over-pack surface, but it had a considerable effect on the temperature rise of the components of the over-pack body. As the screen mesh size decreased, the heat removal by the natural convection cooling through the passive heat-removal system was reduced, and the temperature of the concrete storage cask rose.
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ASME 2016 Pressure Vessels and Piping Conference
July 17–21, 2016
Vancouver, British Columbia, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5045-9
PROCEEDINGS PAPER
Heat Removal Performance in Accordance With Mesh Size of Screen Installed at Opening of the Inlets and Outlets of Concrete Storage Cask
Kyoung-Sik Bang,
Kyoung-Sik Bang
Korea Atomic Energy Research Institute, Daejeon, Korea
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Seung-Hwan Yu,
Seung-Hwan Yu
Korea Atomic Energy Research Institute, Daejeon, Korea
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Ju-Chan Lee,
Ju-Chan Lee
Korea Atomic Energy Research Institute, Daejeon, Korea
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Ki-Seog Seo,
Ki-Seog Seo
Korea Atomic Energy Research Institute, Daejeon, Korea
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Woo-Seok Choi
Woo-Seok Choi
Korea Atomic Energy Research Institute, Daejeon, Korea
Search for other works by this author on:
Kyoung-Sik Bang
Korea Atomic Energy Research Institute, Daejeon, Korea
Seung-Hwan Yu
Korea Atomic Energy Research Institute, Daejeon, Korea
Ju-Chan Lee
Korea Atomic Energy Research Institute, Daejeon, Korea
Ki-Seog Seo
Korea Atomic Energy Research Institute, Daejeon, Korea
Woo-Seok Choi
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
PVP2016-63430, V007T07A034; 7 pages
Published Online:
December 1, 2016
Citation
Bang, K, Yu, S, Lee, J, Seo, K, & Choi, W. "Heat Removal Performance in Accordance With Mesh Size of Screen Installed at Opening of the Inlets and Outlets of Concrete Storage Cask." Proceedings of the ASME 2016 Pressure Vessels and Piping Conference. Volume 7: Operations, Applications and Components. Vancouver, British Columbia, Canada. July 17–21, 2016. V007T07A034. ASME. https://doi.org/10.1115/PVP2016-63430
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