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Development of High Performance Clarification System for FBR Dissolver Liquor
Abstract:A high performance clarification system has been discussed for advanced aqueous reprocessing of FBR spent fuel. Dissolver residue gives the cause of troubles on the plant operation of reprocessing. In this study, the new clarification system based on the hybrid of centrifuge and filtration was proposed to get the high separation ability of the component of whole insoluble sludge. The clarification tests of simulated solid species were carried out to evaluate the clarification performance using small-scale test apparatus of centrifuge and filter unit. The density effect of solid species on the collection efficiency was mainly evaluated in the centrifugal clarification test. In the filtration test using ceramic filter with pore size of 0.2μm, on the other hand, permeability and filtration rate were evaluated in addition to the filtration efficiency. As results, it was evaluated that the collection efficiency of solid species on the new clarification system was estimated as nearly 100%. In conclusion, the high clarification performance of dissolver liquor can be achieved by the hybrid of the centrifuge and filtration system.
Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1055597Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 1284
 Atomic energy commission, "Treatment and recycling spent nuclear fuel", Le Moniteur, 2008 (in French).
 T. Koyama, T. Washiya, H. Nakabayashi and H. Funasaka, "Current status on reprocessing technology of fast reactor fuel cycle technology development (FaCT) project in Japan", Proc. Global 2009, Paris, France, 2009, Paper 9100.
 T. Takata, Y. Koma, K. Sato, M. Kamiya, A. Shibata, K. Nomura, H. Ogino, T. Koyama and S. Aose, "Conceptual design study on advanced aqueous reprocessing system for fast reactor fuel cycle", J.Nucl.Sci.Tech., Vol.41, 2004, pp307-314.
 T. Washiya, M. Tasaka, T. Kitagaki, H. Higuchi, T. Kobayashi and T. Koyama, "Development of mechanical disassembly and shearing systems for FBR spent fuel in FaCT project," Proc. Global 2009, Paris, France, 2009, Paper 9245.
 A. Shibata, N. Kaji, M. Nakahara, K. Yano, T. Tayama, K. Nakamura, T. Washiya, M. Myochin, T. Chikazawa and T. Kikuchi, "Current status on research and development of uranium crystallization system in advanced aqueous reprocessing of FaCT project", Proc. Global 2009, Paris, France, 2009, Paper 9154.
 H. Kleykamp, "The chemical state of fission products in oxide fuels at different stages of the nuclear fuel cycle," Nucl. Tech., 80, 1988, pp412-422.
 H. Kleykamp, "Post-irradiation examinations and composition of the residues from nitric acid dissolution experiments of high-burnup LWR fuel," J. Nucl. Mater., 171, 1990, pp181-188.
 T. Adachi, M. Ohnuki, N. Yoshida, T. Sonobe, W. Kawamura, H.Takeishi, K. Gunji, T. Kimura, T. Suzuki, Y. Nakahara, T. Muromura, Y. Kobayashi, H. Okashita and T. Yamamoto "Dissolution study of spent PWR fuel: Dissolution behavior and chemical properties of insoluble residues," J. Nucl. Mater., 174, 1990, pp60-71.
 A. Magnaldo, M. Masson and R. Champion, "Nucleation and crystal growth of zirconium molybdate hydrate in nitric acid", Chem. Eng., 62, 2007, pp766-774.
 J. Lausch, R. Berg, L. Koch, M. Coquerelle, J. P. Glatz, C.T. Walker and K. Mayer, "Dissolution residues of highly burnt nuclear fuels", J. Nucl. Mater., 208, 1994, pp73-80.
 B.S.M. Rao, E. Gantner, J. Reinhardt, D. Steinert and H.J. Ache, "Characterization of the solids formed from simulated nuclear fuel reprocessing solutions", J. Nucl. Mater., 170, 1990, pp39-49.
 A. Togashi, T. Sakai, K. Kikuchi, O. Toyoda and S. Nemoto, "Study of insoluble sludge on reprocessing test of FBR spent fuel", PNC-TN8410 93-080 (1993).
 K. Yamada, T.Shirai, M. Wada and H. Nakamizo, "Applicability study on a ceramic filter with hot-test conducted in a BWR plant", RECOD-91, 1991, pp1150-1154.