경사충격을 받는 방사성 물질 운반용기의 구조 건전성에 관한 연구
A Study on the Structural Integrity of the Transport Cask for the Radioactive Material under Oblique Impact
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참고문헌
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초록
In this paper, as the transport cask was moved in the reactor, the structural integrity on the cask had to be evaluated in the normal transport condition. The drop height of the cask was determined bythe weight of the cask in the normal transport condition by regulations about assessment test. It was determined that the drop height of the cask was 1.2 m by regulations. The velocity of the drop impact was calculated to perform the drop impact analysis by the principle of the conservation of energy. Using results of the simulation about the drop impact analysis, the structural integrity assessment on the transport cask was performed by ASME Boiler and Pressure Vessel Code.
Abstract
In this paper, as the transport cask was moved in the reactor, the structural integrity on the cask had to be evaluated in the normal transport condition. The drop height of the cask was determined bythe weight of the cask in the normal transport condition by regulations about assessment test. It was determined that the drop height of the cask was 1.2 m by regulations. The velocity of the drop impact was calculated to perform the drop impact analysis by the principle of the conservation of energy. Using results of the simulation about the drop impact analysis, the structural integrity assessment on the transport cask was performed by ASME Boiler and Pressure Vessel Code.
참고문헌 (11)
- Nuclear Safety and Security Commission, "Technology Standards for Packing and Transport of Radioactive Materials", Nuclear Safety Bureau of Nuclear Safety and Security Commission, ~ (2011)
- IAEA, "Regulations for the Safe Transport of Radioactive Material", IAEA Safety Standards Series, ~ (2012)
- The American Society of Mechanical Engineers, "Containments for Transportation and Storage of Spent Nuclear Fuel and High Level Radioactive Material and Waste", 2007 ASME Boiler & Pressure Vessel Code, Section Ⅲ, Division 3, ~ (2007)
- Park, K.N., "Fabrication of Pressure Vessel for the Fuel Irradiation Test", Journal of Korean Society of Mechanical Technology, 9(3), pp.59~64 (2007)
- Park, K.N., "Shape Design of In-Pool Parts Vessel Assembly for Fuel Test Loop", Journal of Korean Society of Mechanical Technology, 6(1), pp.157~165 (2004)
- Saito, Y., "Containment Integrity Evaluation of MSF-type Cask for Interim Storage and Transport of PWR Spent Fuel", International Journal of Pressure Vessels and Piping, 117-118, pp.33~41 (2014)
- 이상훈, "Impact Analyses and Tests of Concrete Overpacks of Spent Nuclear Fuel Storage Casks", Nuclear Engineering and Technology, 46(1), pp.73~80 (2014), 한국원자력학회
- Analysis Technology on the Thick Plate Free Drop Impact, Heat and Thermal Stress of the Cask for Radioactive Material Transport, "Lee, Y.S.", KINS, ~, pp.KINS (2002), HR-443
- Safety Analysis Report for Hot Cell Transport Cask, "Choi, W.S.", KAERI, ~, pp.KAERI-TR-4287 (2011), 2011
- The American Society of Mechanical Engineers, "Properties(Metric)", 2007 ASME Boiler &Pressure Vessel Code, Section Ⅱ, Part D, ~ (2007)
- "LS-DYNA Version 970 Keyword User's Manual", Livermore Software, ~