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Industrial tests on the electrochemical separation of uranium and plutonium in reprocessing spent fuel by aqueous methods

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References

  1. V. I. Marchenko, “State of the art and development prospects in electrochemical methods in spent-fuel reprocessing technology,” At. Tekh. Rubezhom, No. 2, 3–11 (1987).

    Google Scholar 

  2. H. Schmieder and H. Goldacker, “Technical scale electroredox equipment for the separation of plutonium,” in: Proc. ISEC'86. Munich. FRG. Vol. 1 (1986), pp. 117–129.

  3. M. Ozawa, S. Nemoto, Y. Ueda, et al., “Salt-free purex process development,” in: Proc. RECOD'91. Sendai, Japan, Vol. 2 (1991), pp. 729–731.

  4. He Jianyu, Zhang Qingxuan. Luo Longjun, and Tian Baosheng. “Application of electroreduction and oxidation technique in reprocessing of nuclear fuels in China,” ibid., Proc. RECOD'91. Sendai, Japan, Vol. 2 (1991), pp. 698–703.

  5. K. Kim, J. Kim, H. Aoyagi, and Z. Yoshida, “Kinetics of reduction of uranium (VI) to uranium (IV) at titanium electrode in nitric acid and hydrazine media.” J. Nucl. Sci. Technol.,31, No. 4, 329–334 (1994).

    Article  Google Scholar 

  6. J. Hindman, D. Cohen, and J. Sullivan, in: Proc. of the International Conf. on the Peaceful Use of Atomic Energy, Geneva, 1955 [Russian translation], Goskhimizdat, Moscow (1958) V. 7, p. 427.

    Google Scholar 

  7. V. S. Koltunov, V. I. Marchenko, A. S. Nikiforov, et al., “Role of technetium in redox processes in irradiated-fuel technology,” At. Énerg.,61, No. 1, 35–41 (1986).

    Google Scholar 

  8. J. Garraway and P. Wilson, “The technetium-catalysed oxidation of hydrazine by nitric acid,” J. Less-Common Metals, No. 2, 191–203 (1989).

    Google Scholar 

  9. V. I. Marchenko, V. N. Rubisov, V. V. Revyakin, and V. S. Shmidt, “Simulation of reductive re-extraction of plutonium by quadrivalent uranium in discrete-type apparatus,” At. Énerg.,62, No. 2, 88–90 (1987).

    Google Scholar 

  10. V. I. Marchenko, V. N. Rubisov, V. S. Koltunov, and T. V. Gomonova, “Simulating the reductive re-extraction of plutonium by electrochemically generated uranium(IV),” At. Énerg.,67, No. 5, 459–462 (1992).

    Google Scholar 

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State Research Institute of the Russian Federation and Bochvar All-Russia New Materials Research Institute. The Mayak Corporation. Translated from Atomnaya Énergiya, Vol. 82, No. 2, pp. 155–157, February, 1997.

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Marchenko, V.I., Polunin, A.K., Zakharkin, B.S. et al. Industrial tests on the electrochemical separation of uranium and plutonium in reprocessing spent fuel by aqueous methods. At Energy 82, 152–155 (1997). https://doi.org/10.1007/BF02413469

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