Development of High Performance Clarification System for FBR Dissolver Liquor
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.
[1] Atomic energy commission, "Treatment and recycling spent nuclear fuel",
Le Moniteur, 2008 (in French).
[2] 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.
[3] 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.
[4] 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.
[5] 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.
[6] 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.
[7] 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.
[8] 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.
[9] A. Magnaldo, M. Masson and R. Champion, "Nucleation and crystal
growth of zirconium molybdate hydrate in nitric acid", Chem. Eng., 62,
2007, pp766-774.
[10] 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.
[11] 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.
[12] 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).
[13] 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.
[1] Atomic energy commission, "Treatment and recycling spent nuclear fuel",
Le Moniteur, 2008 (in French).
[2] 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.
[3] 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.
[4] 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.
[5] 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.
[6] 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.
[7] 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.
[8] 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.
[9] A. Magnaldo, M. Masson and R. Champion, "Nucleation and crystal
growth of zirconium molybdate hydrate in nitric acid", Chem. Eng., 62,
2007, pp766-774.
[10] 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.
[11] 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.
[12] 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).
[13] 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.
@article{"International Journal of Chemical, Materials and Biomolecular Sciences:50790", author = "M.Takeuchi and T.Kitagaki and Y.Noguchi and T. Washiya", title = "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.", keywords = "Centrifuge, Clarification, FBR dissolver liquor, Filtration", volume = "5", number = "9", pages = "749-7", }