Evaluation of the KN-12 Spent Fuel Transport Cask by Analysis |
Chung, Sung-Hwan
(Nuclear Environment Techonlogy Institute)
Lee, Heung-Young (Nuclear Environment Techonlogy Institute) Song, Myung-Jae (Nuclear Environment Techonlogy Institute) Rudolf Diersch (Gesellschaft fur Nuklear Behalter mbH (GNB)) Reiner Laug (Gesellschaft fur Nuklear Behalter mbH (GNB)) |
1 | International Atomic Energy Agency, IAEA Safety Standards Series No.ST-1, 'Regulations for the Safe Transport of Radioactive Material' (1996) |
2 | US, 10 CFR Part 71, 'Packaging and Transportation of Radioactive Material' (1997) |
3 | Korea Ministry of Science and Technology, 'Korea Atomic Energy Act' (1999) |
4 | Americal Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section HI, Division 3, 'Containment Systems and Transport Packagings for Spent Nuclear Fuel and High Level Radioactive Waste' (1998) |
5 | American National Standards Institute, 'Special Lifting Devices for Shipping Containers Weighing 10,000Ibs(4,500kg) or More' (1986) |
6 | US Nuclear Regulatory Commission, Regulatory Guide 7.8, 'Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material' (1989) |
7 | US Nuclear Regulatory Commission, Regulatory Guide 7.6, 'Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels' (1978) |
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