Development of argon gas cleaning for sodium-cooled reactor spent fuel

References

• Uto , N , Sakai , T , Mihara , T , Toda , M , Kotake , S and Aoto , K . 2009 . “ Conceptual design for Japan sodium-cooled fast reactor (1) current status for system design for JSFR ” . In Proceedings of the International Congress on Advances in Nuclear Power Plants Tokyo , , Japan
   Google Scholar
• Usui , S , Mihara , T , Obara , H and Kotake , S . 2009 . “ Development of advanced loop-type fast reactor in Japan ” . In Proceedings of the International Congress on Advances in Nuclear Power Plants Tokyo , , Japan
   Google Scholar
• Chikazawa , Y , Uzawa , M , Usui , S , Tozawa , K and Kotake , S . 2012 . Comparison of sodium-cooled reactor fuel-handling systems with and without an ex-vessel storage tank . Nucl Technol , 177 : 293 – 302 .
   Web of Science ®Google Scholar
• Katoh , A , Chikazawa , A and Uzawa , M . 2012 . “ Evaluation and improvement on external-hazard proof of JSFR fuel handling system ” . In Proceedings of the International Congress on Advances in Nuclear Power Plants Chicago , IL
   Google Scholar
• Suzuki , F , Nagahiro , Y , Funato , H , Fujiki , K and Inoue , T . 1991 . “ Design and construction of the fuel handling and storage facility for the fast breeder reactor Monju ” . In Proceedings of the International Conference on Fast Reactors and Related Fuel Cycles Kyoto , , Japan
   Google Scholar
• Mizuno , T and Niwa , H . 2004 . Advanced MOX core design study of sodium-cooled reactor in current feasibility study on commercialized fast reactor cycle system in Japan . Nucl Technol , 146 : 155 – 163 .
   Web of Science ®Google Scholar
• Chikazawa , Y , Hori , T , Usui , S , Aizawa , K , Konomura , M and Nishiguchi , Y . 2005 . “ Design study on a fuel handling system in a sodium cooled reactor ” . In JNC TY9400 2005–009 , Japan : Japan Nuclear Cycle Development Institute . Japanese
   Google Scholar
• Yorihisa , K and Sato , I . 1979 . “ Experimental fast reactor JOYO fundamental test– performance test of the fuel cleaning facility ” . In PNC TN941 79–41(3) , Japan : Power Reactor and Fuel Development Corporation . Japanese
   Google Scholar
• Suzuki , T , Ito , H , Ebata , K and Kuno , S . 1991 . “ Operational experience of the fuel cleaning facility in JOYO ” . In PNC TN9410 91–155 , Japan : Japan Nuclear Cycle Development Institute . Japanese
   Google Scholar
• Monju Construction Office . 1996 . “ Operation and maintenance experience on the fuel handling systems and storage facilities of MONJU (1) ” . In PNC TN2410 96–005 , Japan : Japan Nuclear Cycle Development Institute . Japanese
   Google Scholar
• Obata , H , Taniguchi , H , Iseki , A , Ohuchi , K , Matsusaka , M and Nagahiro , Y . 1992 . “ Sodium cleaning test by spent fuel cleaning system ” . In Transaction of the 1992 Fall Meeting of the Atomic Energy Society of Japan Vol. B14 , Nagoya , , Japan Japanese
   Google Scholar
• Narita , T , Ukai , S , Kaito , T , Ohtsuka , S and Matsuda , Y. 2008 . Water corrosion resistance of ODS Ferritic-Martensitic steel tubes . J Nucl Sci Technol. , 45 : 99 – 102 . doi: 10.1080/18811248.2008.9711419
   Google Scholar