Thermal Evaluation of the KN-12 Transport Cask |
Chung, Sung-Hwan
(Nuclear Environment Technology Institute (NETEC), KHNP)
Chae, Kyoung-Myoung (Nuclear Environment Technology Institute (NETEC), KHNP) Choi, Byung-Il (Nuclear Environment Technology Institute (NETEC), KHNP) Lee, Heung-Young (Nuclear Environment Technology Institute (NETEC), KHNP) Song, Myung-Jae (Nuclear Environment Technology Institute (NETEC), KHNP) |
1 | International Atomic Energy Agency, IAEA Safety Standards Series No.ST-1, 'Regulations for the Safe Transport of Radioactive Material' (1996) |
2 | Korea Hydro and Nuclear Power Co. Ltd., 'Safety Tests Procedures', PT-351-G-T-P-001 Rev. 1 (2001) |
3 | Livermore Software Technology Corporation, 'LS-DYNA3D User's Manual Version 950' (1999) |
4 | Korea Ministry of Science and Technology, 'Korea Atomic Energy Act' (2001) |
5 | The American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, Division 3, 'Containment Systems and Transport Packagings for Spent Nuclear Fuel and High Level Radioactive Waste' (1998) |
6 | 10 CFR Part 71, 'Packaging and Transportation of Radioactive Material' (1997) |
7 | Korea Hydro and Nuclear Power Co. Ltd., 'KN-12 Spent Nuclear Fuel Transport Cask Safety Analysis Report', PT-361-G-A-R-002 Rev. 0 (2002) |
8 | Korea Hydro and Nuclear Power Co. Ltd., 'Heat Transfer Test Procedure of the KN-1 Cask', PT-371-H-T-P-007 Rev. 1 (2002) |
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