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Gas-Fluoride Technology for Processing Spent Oxide Fuel

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Abstract

The scientific-research work on reprocessing spent oxide fuel by gas-fluoride method is reviewed. The refining possibilities of the basic stages of gas-fluoride technology are studied. The possibility of separating most fission products from the ashes at the fluoridation stage is confirmed experimentally. The use of fluoride sorbents (NaF, BaF2) permits reaching a total coefficient of removal of fission products from UF6 at the 107 level. It is shown that deep extraction of plutonium from oxide fuel is possible. The results of investigations on pyrohydrolysis of UF6 and a mixture of UF6 with PuF6 with production of granulate of the oxides with the required density with fluorine content 0.005 mass % and oxygen coefficient 2–2.1 are presented.

Recommendations for use of gas-fluoride technology for reprocessing spent oxide fuel from fast and light-water reactors are given taking account of the new requirements for nonproliferation of fissioning materials, and a prediction is given for a closed nuclear fuel cycle using gas-fluoride technology and separation of Np, Am, and Cm for transmutation with the aid of easily melting fluoride melts. 1 figure, 5 tables, 27 references.

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REFERENCES

  1. N. P. Galkin, A. A. Maiorov, U. D. Veryatin, et al., Chemistry and Technology of Uranium Fluoride Compounds [in Russian], Gosatomizdat, Moscow (1961).

    Google Scholar 

  2. A. Jonke, “Reprocessing of nuclear fuel reactors by processes based on volatilization, fractional distillation, and selective adsorption,” At. Energ. Rev., 3, No. 1, 1-60 (1965).

    Google Scholar 

  3. J. Schmetz, Reprocessing of Nuclear Fuels by Fluoride Volatility Process, Federal Republic of Germany, Karlsruhe, August 1969.

  4. B. V. Shevchenko (ed.), Chemical Reprocessing of Irradiated Nuclear Fuel [in Russian], Atomizdat, Moscow (1973).

    Google Scholar 

  5. N. P. Galkin, L. A. Ponomarev, and Yu. D. Shishkov, Plutonium Hexafluoride: Production and Properties [in Russian], Gosatomizdat, Moscow (1961).

    Google Scholar 

  6. N. P. Galkin, L. A. Ponomarev, and Yu. D. Shishkov, “Investigation of processes of separation of uranium and plutonium hexafluorides,” Radiokhim., 22, No. 5, 754-757 (1990).

    Google Scholar 

  7. U. D. Veryatin, N. P. Galkin, G. N. Novoselov, et al., “Basic problems of the fluoride method for reprocessing fuel elements from nuclear power plants based on fast neutrons,” At. Énerg., 31, No. 4, 375-382 (1971).

    Google Scholar 

  8. U. D. Veryatin, N. P. Galkin, V. A. Zuev, et al., “Investigation of the fluoride method of recovery of oxide fuel,” in: Proceedings of a Symposium of the Council for Mutual Economic Aid, Marianske-Lazne, Czechoslovakia (1972), Vol. 1, pp. 271-279.

    Google Scholar 

  9. U. D. Veryatin, N. P. Galkin, V. A. Zuev, et al., “Investigation of the fluoride method of recovery of oxide fuel,” in: Proceedings of the 3rd Symposium of the Council of Mutual Economic Aid, March 24-26, 1974, pp. 298-304.

  10. N. P. Galkin, M. B. Seregin, E. F. Lednev, et al., “Interaction of uranium hexafluoride with fluorides of alkali and alkaline-earth metals and thermal decomposition of the complex salts formed,” in: Report at the 1st All-Union Conference on Uranium Chemistry (1974).

  11. V. A. Zuev and V. I. Lomov, Plutonium Hexafluoride [in Russian], Atomizdat, Moscow (1975).

    Google Scholar 

  12. N. P. Galkin, V. A. Zaitsev, and M. B. Seregin, Catching and Reprocessing of Fluorine-Containing Gases [in Russian], Atomizdat, Moscow (1975).

    Google Scholar 

  13. U. D. Veryatin, N. P. Galkin, V. A. Zuev, et al., “Investigation of the behavior of fission products in application to the fluoride method for the recovery of oxide fuel,” Radiokhim., 18, 877-885 (1976).

    Google Scholar 

  14. U. D. Veryatin, V. F. Kharin, and V. A. Zuev, “Development of methods for fluoridation of nuclear fuel, including condensation of the gaseous fluorides formed,” in: Proceedings of the 4th Symposium of the Council of Mutual Economic Aid, Karlovy Vary, Czechoslovakia (1977).

  15. N. P. Galkin,V. I. Khomyakov, and V. F. Kharin, “Investigation of the behavior of volatile radioactive impurities during purification of uranium-containing materials by the fluoridation method,” Radiokhim., No. 5, 758-762 (1980).

  16. N. P. Galkin, U. D. Veryatin, I. F. Yakhonin, et al., “Investigation of the transformation of uranium hexafluoride into dioxide,” At. Énerg., 52, No. 1, 36-39 (1982).

    Google Scholar 

  17. V. I. Shcherbakov, V. A. Zuev, and A. V. Parfenov, Kinetics and Mechanism of Fluoridation of Uranium, Plutonium, and Neptunium Compounds by Fluorine and Halogen-Fluorides [in Russian], Énergoatomizdat, Moscow (1985).

    Google Scholar 

  18. V. A. Zuev and V. T. Orekhov, Actinide Hexafluorides [in Russian], Énergoatomizdat, Moscow (1991).

    Google Scholar 

  19. V. V. Shatalov, M. B. Seregin, V. F. Kharin, and L. A. Ponomarev, “Gas fluoride technology for reprocessing irradiated oxide fuel,” in: Abstracts of Reports at the 1st International Forum on High Technologies for the Defense Complex, Moscow, April 17-21, 2000, p. 33.

  20. “A conceptual design study of a fluoride-volatility plant for reprocessing LMFBR fuels,” USA, ANL-7583 (1969).

  21. E. O. Adamov (ed.), White Book of Nuclear Power [in Russian], NIKIÉT, Moscow (1998).

    Google Scholar 

  22. E. O. Adamov, I. Kh. Ganev, A. V. Lopatkin, et al., Transmutation Fuel Cycle for Nuclear Power in Russia [in Russian], NIKIÉT, Moscow (1999).

    Google Scholar 

  23. Strategy for the Development of Nuclear Power in Russia in the First Half of the Twenty-First Century. Basic Assumptions [in Russian], Ministry of Atomic Energy of the Russian Federation, Moscow (2001).

  24. V. A. Tsykanov, A. A. Maershin, A. A. Petukhov, et al., “Analysis of the working capacity of fuel elements of a BOR-60 reactor with vibrationally compacted uranium-plutonium oxide fuel,” At. Énerg., 66, No. 5, 299-302 (1989).

    Google Scholar 

  25. M. Takahashi, T. Fukasawa, T. Sawa, et al., “Improved fluoride volatility reprocessing for MOX fuel cycle,” in: International Conference, Atlante-2000, Avignon, France, October 24-28, 2000.

  26. A. Florin, J. Tannenbaum, and J. Lemons, J. Inorg. and Nucl. Chem., No. 5, 6, 368.

  27. V. M. Novikov, V. V. Ignat'ev, V. I. Fedulov, et al., Liquid-Salt Nuclear Power Systems: Prospects and Problems [in Russian], Énergoatomizdat, Moscow (1990).

    Google Scholar 

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Authors
  1. V. V. Shatalov
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  2. M. B. Seregin
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  3. V. F. Kharin
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  4. L. A. Ponomarev
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Shatalov, V.V., Seregin, M.B., Kharin, V.F. et al. Gas-Fluoride Technology for Processing Spent Oxide Fuel. Atomic Energy 90, 224–234 (2001). https://doi.org/10.1023/A:1011376412282

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