Literature Cited
V. I. Zemlyanukhin, E. I. Il'enko, A. N. Kondrat'ev, et al., Radiochemical Reprocessing of Nuclear Power Station Fuel [in Russian], Énergoatomizdat, Moscow (1989).
A. S. Nikiforov, V. S. Shmidt, and B. S. Zakharkin, “Radiochemical reprocessing of spent fuel,” in: Nuclear Science and Engineering in the USSR [in Russian], Énergoatomizdat, Moscow (1987).
V. S. Koltunov, V. I. Marchenko, A. S. Nikiforov, et al., “The role of technetium in redox processes in irradiated-fuel reprocessing,” At. Énerg.,60, No. 1, 35–41 (1986).
G. Petrich, Intern. Solv. Extr. Conf., ISEC-86, Munich, FRG, Vol. 1 (1986).
J. Geldard, A. Beyerlein, and Houn-Lin Chin, Nucl. Technol.,75, No. 2, 160 (1986).
V. N. Rubisov and A. S. Solovkin, “Simulating the purex process with allowance for effects on the equilibrium from di-n-butylphosphoric acid (weak acid actinoid reextraction),” At. Énerg.,63, No. 1, 23–26 (1987).
J. Garraway, P. Wilson, and G. Less, Commun. Met.,97, No. 1, 191 (1984).
A. M. Rozen, B. S. Zakharkin, A. Yu. Vakhrushin, and V. S. Vlasov, “A model for the solvent extraction of traces of Tc(VII) by tributylphosphate,” At. Énerg.,63, No. 3, 175–178 (1987).
D. Gourisse and A. Gautier, J. Inorg. Nucl. Chem.,31, No. 3, 839 (1969).
H. Schmieder and H. Goldacker, Atomkernenergie-Kerntechnik,33, No. 4, 255 (1979).
Additional information
Bochvar All-Union Nuclear Materials Research Institute. Translated from Atomnaya Énergiya, Vol. 72, No. 5, pp. 459–462, May, 1992.
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Marchenko, V.I., Rubisov, V.N., Koltunov, V.S. et al. Simulating the reductive reextraction of plutonium by electrochemically generated U(IV). At Energy 72, 408–411 (1992). https://doi.org/10.1007/BF00761229
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DOI: https://doi.org/10.1007/BF00761229