ANALYSIS OF HEAT TRANSFER ON SPENT FUEL DRY CASK DURING SHORT-TERM OPERATIONS
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Kim, H.
(R&D Institute, Korea Radioactive Waste Agency)
Lee, D.G. (Nuclear Energy Team, Korea Nuclear Engineering and Service Co.) Kang, G.U. (R&D Institute, Korea Radioactive Waste Agency) Cho, C.H. (R&D Institute, Korea Radioactive Waste Agency) Kwon, O.J. (Dept. of Aerospace Engineering, KAIST) |
1 | 2014, US Government, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High Level Radioactive Waste and Reactor-Related Greater than Class C waste. 10 CFR 72. |
2 | 2000, US Nuclear Regulatory Commission (NRC), Standard Review Plan for Spent Fuel Dry Storage Facilities. NUREG-1567. |
3 | 2009, US Nuclear Regulatory Commission (NRC), Standard Review Plan for Dry Cask Storage Systems. NUREG-1536. |
4 | 2014, Ministry of Trade, Industry and Energy(MOTIE), Technology Development of Optimization for Spent Nuclear Fuel Storage and Transportation System, Phase 2 Report. |
5 | 1985, Rohsenow, W.M., Hartnett, J.P. and Ganic, E.N., Handbook of Heat Transfer Fundamentals, 2nd Edition. |
6 | 2010, Holtec International Inc., Final Safety Analysis Report for the HI-STORM 100 Cask System, Rev.9. |
7 | 2010, AREVA Inc., Final Safety Analysis Report for the NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel. |
8 | 2014, Kim, H., Kwon, O.J., Kang, G.U. and Lee, D.G., "Comparisons of prediction methods for peak cladding temperature and effective thermal conductivity in spent fuel assemblies of transportation/storage casks," Annals of Nuclear Energy, Vol.71. |
9 | 1996, Bahney, R.H. and Lotz, T.L., Spent Nuclear Fuel Effective Thermal Conductivity Report, Rev.0. |
10 | 2016, Kim, H., Kang, G.U. and Cho. C.H., "Comparisons of Peak Cladding Temperature and Effective Thermal Conductivity: CFD Simulation on PWR Spent Fuel Assemblies," WM2016. |
11 |
2006, BNG Fuel Solutions Corporation, Final Safety Analysis Report for the FuelSolutions |
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