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NTIS 바로가기Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.42 no.3, 2010년, pp.237 - 248
Saegusa, T. (Central Research Institute of Electric Power Industry (CRIEPI)) , Shirai, K. (Central Research Institute of Electric Power Industry (CRIEPI)) , Arai, T. (Central Research Institute of Electric Power Industry (CRIEPI)) , Tani, J. (Central Research Institute of Electric Power Industry (CRIEPI)) , Takeda, H. (Central Research Institute of Electric Power Industry (CRIEPI)) , Wataru, M. (Central Research Institute of Electric Power Industry (CRIEPI)) , Sasahara, A. (Central Research Institute of Electric Power Industry (CRIEPI)) , Winston, P.L. (Idaho National Laboratory (INL))
The safety of metal cask and concrete cask storage technology has been verified by CRIEPI through several research programs on demonstrative testing for the interim storage of spent fuel. The results have been reflected in the safety requirements for dry casks issued by NISA/METI (Nuclear and Indust...
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Atomic Energy Commission of the Japanese Government, "Framework for Nuclear Energy Policy", (2005).
Nuclear and Industrial Safety Agency of the Japanese Government, "Technical Requirements on Interim Spent Fuel Storage Facility Using Dry Metal Cask", NISA-314c-06-02, (in Japanese), (2006).
Nuclear and Industrial Safety Agency of the Japanese Government, "Technical Requirements on Interim Spent Fuel Storage Facility Using Dry Concrete Cask" NISA-314c-06-01, (in Japanese), (2006).
H. Takeda, et. al., "Heat Removal Verification Tests Using Concrete Casks under Normal Condition", NED 238, pp.1196-1205, (2008)
M. Wataru, et. al., " Heat Removal Verification Tests of Full-Scale Concrete Casks under Accident Conditions ", NED 238, pp.1206-1212, (2008)
Japan Society of Mechanical Engineers, "Code for Construction of Spent Nuclear Fuel Storage Facilities ?Rule on Concrete Casks, Canister Transfer Machines and Canister Transport Casks for Spent Nuclear Fuel ?", JSME S FB1-2003, (2003).
K. Shirai, et. al., "Demonstrative Drop Tests of Transport and Storage Full-Scale MPCs with High Corrosionresistant material", NED 238, pp.1241-1249, (2008)
K. Shirai, et al., Experimental Studies of Free-Standing Spent Fuel Storage Cask subjected to Strong Earthquake, Proc. of the 15th Int. Symposium on the Packaging and Transportation of Radioactive Materials, PATRAM 2007, Miami, Florida, USA (2007).
Nuclear Safety Commission of the Japanese Government, "Regulatory Guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities", Sep., (2006)
J. Tani and M. Mayuzumi, "Stress corrosion cracking of canister materials for storage of spent nuclear fuel (Vol.2) ? An evaluation of the possibility of SCC initiation-", CRIEPI Report Q08007(2009)(in Japanese)
H. Takeda, et.al., " Leakage Evaluation of Metal Cask during Drop Test ", Proc. of GLOBAL 2005, No.575, Tsukuba, Japan, (2005).
K. Shirai, et al., Safety Analysis of Dual Purpose Metal Cask Subjected to Impulsive Loads due to Aircraft Engine Crash, Proc. of ICONE16, Int. Conference on Nuclear Engineering, Orland, Florida, USA, (2008)
A. Sasahara and T. Matsumura, "Post-irradiation examination focused on fuel integrity of spent BWRMOX and PWR-UO2 fuels stored for 20 years", Nucl. Eng. Design, Vol. 238, p.1250-1259 (2008).
S. Itooka, et al, "Supporting Study of Regulation for Interim Storage Facility for Spent Fuel in Japan", Proc. ICONE 13-50617, Beijing, China, May 16-20, 2005.
K. Ito, K. Kamimura, Y. Tsukuda, Y., "Evaluation of Irradiation Effect on Spent Fuel Cladding Creep Prpperties", Proc. 2004 Int’l Mtg on LWR Fuel Performance, Orlando, Florida, Sept.19-22, 2004. Paper 1117.
M. Aomi, et al, "Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High Burnup Fuel Cladding Tubes in Interim Dry Storage ", Journal of ASTM international (2008).
Transport and Storage WGs in NISA/METI of the Japanese Government, "Long-term Integrity of Dry Metal Cask and Contents for Interim Storage Facility of Spent Fuel using Dry Metal Cask", June 25, 2010.
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