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REVIEW AND FUTURE ISSUES ON SPENT NUCLEAR FUEL STORAGE 원문보기

Nuclear 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))

Abstract AI-Helper 아이콘AI-Helper

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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제안 방법

  • The test MPC was slightly deformed near the impacted area. He leak tests were performed before and after the drop tests to confirm the integrity of the leak-tightness of the test MPCs (especially welded lids) against impact loads. Measured leakage rates showed the integrity of the leak-tightness at the lids and MPC shell, as all values were under 1.
  • Key issues of these studies include the safety requirements in the operation and maintenance during spent fuel storage and unloading/loading for transportation, long-term integrity of metal canisters and concrete materials, etc. In 1997, CRIEPI completed the research program of the demonstration test for the interim storage of spent fuel, mainly involving concrete cask storage technologies, to reflect the technical requirements issued by NISA.
  • The JNES tests were composed of hydride effect evaluation testing, irradiation hardening recovery testing, and creep testing. In hydride effect evaluation testing, hydride reorientation testing has been performed in order to evaluate the correlation between hydride reorientation behavior and conditions, such as hoop stress, temperature, and cooling rate for BWR and PWR irradiated cladding tubes.
  • The report describes alternative measures for the visual inspection of the fuel basket and spent fuel, and inner pressure measurement. The report concluded that records and documents before and during storage could be alternative measures for the necessary inspections. The report added that more data on the long-term integrity of the metal cask and spent fuel shall be continuously accumulated.
  • Transport/storage working groups of the NISA/METI of the Japanese government have issued a report19. The report describes alternative measures for the visual inspection of the fuel basket and spent fuel, and inner pressure measurement. The report concluded that records and documents before and during storage could be alternative measures for the necessary inspections.
  • s. Two drop tests in the horizontal and vertical orientations were conducted considering non-mechanistic drop or impact events during handling, and the drop heights were 1m and 6m, respectively. Regarding contents of MPC, dummy steel structures equal to the total weights of the spent fuels (14.
  • Two types of concrete casks, a reinforced-concrete cask (RC cask) and concrete-filled-steel cask (CFS cask) to store the high burn-up spent fuel, were designed. The preliminary designs for the two types of cask, the RC cask and CFS cask, were employed as the basic structure, as shown in Fig.

대상 데이터

  • In the type-II model, the cask body is made of ductile cast iron, and the lid is made of stainless steel. In this model, an inner metal gasket (enveloped with silver), and an outer rubber gasket (silicone rubber) were installed. In both models, the test temperature (130~140℃ at the secondary lid) was maintained with the electrical heaters installed in the cask cavities.
  • In the I-type model, the cask body and lid are made of forged carbon steel. The sealing surface is overlaid with stainless steel welding (SUS304), and a double metal gasket (enveloped with aluminium) is installed. In the type-II model, the cask body is made of ductile cast iron, and the lid is made of stainless steel.
  • 16 shows overview of a full-scale metal cask model for impact analysis. This model has been designed as metal cask for dry storage and transportation installing 21 PWR-type fuel assemblies.
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참고문헌 (19)

  1. Atomic Energy Commission of the Japanese Government, "Framework for Nuclear Energy Policy", (2005). 

  2. 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). 

  3. 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). 

  4. H. Takeda, et. al., "Heat Removal Verification Tests Using Concrete Casks under Normal Condition", NED 238, pp.1196-1205, (2008) 

  5. M. Wataru, et. al., " Heat Removal Verification Tests of Full-Scale Concrete Casks under Accident Conditions ", NED 238, pp.1206-1212, (2008) 

  6. 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). 

  7. K. Shirai, et. al., "Demonstrative Drop Tests of Transport and Storage Full-Scale MPCs with High Corrosionresistant material", NED 238, pp.1241-1249, (2008) 

  8. 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). 

  9. Nuclear Safety Commission of the Japanese Government, "Regulatory Guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities", Sep., (2006) 

  10. 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) 

  11. H. Takeda, et.al., " Leakage Evaluation of Metal Cask during Drop Test ", Proc. of GLOBAL 2005, No.575, Tsukuba, Japan, (2005). 

  12. C. Itoh, et al., Long Term Containment Performance Test for Spent Fuel Transport/Storage Casks, Trans. At. Energy Soc. Japan, Vol.2, No.2, pp.158-162, (in Japanese), (2003) 

  13. 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) 

  14. T. Saegusa, M. Mayuzumi, C. Ito, and K. Shirai, "Experimental Studies on Safety of Dry Cask Storage Technology of Spent Fuel- Allowable Temperature of Cladding and Integrity of Cask under Accident-", J. Nucl. Sci. Tech., Vol.33, No.3, p.250-258 (1996). 

  15. 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). 

  16. 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. 

  17. 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. 

  18. 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). 

  19. 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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