Atomic Energy

, Volume 82, Issue 1, pp 70–72 | Cite as

Effect of the degree of denitration on the solubility in a system simulating liquid radiactive wastes for vitrification

  • E. M. Knyazev
  • A. S. Polyakov
Scientific and Technical Reports

Keywords

Radiactive Waste 

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References

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    A. S. Polyakov, G. B. Borisov, N. I. Moiseenko, et al., “Experience in operating the ÉP-500/1R ceramic melter for vitrification of liquid high-level wastes,” At. Énerg.,76, No. 3, 183–188 (1994).Google Scholar
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    Yu. P. Zhirnov, M. I. Zhikharev, A. Ya. Chilikin, and I. Ya. Skripak, “Physical-chemical principles of evaporation and denitration of high-level wastes prior to vitrification,” At. Énerg.,79, No. 6, 423–428 (1994).Google Scholar
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    E. G. Dzekun, B. Ya. Zilberman, E. M. Knyazev, et al., “Evaporation procedures in spent fuel reprocessing,” in: 3nd International Conference on Nuclear Fuel Reprocessing and Waste Management, Sendai, Japan (1991), Vol. 1, pp. 433–435.Google Scholar
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    A. S. Nikiforov, V. V. Kulichenko, and M. I. Zhikharev, Decontamination of Liquid Radioactive Wastes [in Russian] Énergoatomizdat, Moscow (1985).Google Scholar
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    A. G. Kasatkin, Basic Processes and Apparatus of Chemical Technology [in Russian], Khimiya, Moscow (1971).Google Scholar
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    M. M. Viktorov, Graphical Calculations in the Technology of Inorganic Substances [in Russian], Khimiya, Leningrad (1972).Google Scholar

Copyright information

© Plenum Publishing Corporation 1997

Authors and Affiliations

  • E. M. Knyazev
  • A. S. Polyakov

There are no affiliations available

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