Proceedings of the Korean Radioactive Waste Society Conference (한국방사성폐기물학회:학술대회논문집)
- 2017.05a
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- Pages.153-154
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- 2017
Thermal Analysis of Transportation and Storage Cask of Spent Nuclear Fuel for Forced Gas Drying Condition
- Lim, Suk-Nam (SAE-AN ENGINEERING Co.) ;
- Chae, Gyung-Sun (SAE-AN ENGINEERING Co.) ;
- Han, Jae-Hyun (SAE-AN ENGINEERING Co.) ;
- Park, Jae-Seok (SAE-AN ENGINEERING Co.) ;
- Lee, Dong-Gyu (Korea Nuclear Engineering & Service Corporation)
- Published : 2017.05.25
Abstract
The thermal analysis of transportation and storage cask for SNF was conducted during short term loading operations for forced gas drying condition. The fuel cladding temperature in 6 regions of SNF in the cask during the short term loading operations for forced gas drying condition is shown in the Fig. 3. The thermal analysis results of calculated maximum cladding temperature in each process demonstrate that operating scenario of TFD in detailed design maintain well below the temperature limits of
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