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Recovery of Uranium and Plutonium from Spent Fuel Elements of Nuclear Reactors

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Abstract

The results of investigations of the preliminary removal of the products of radioactive decomposition from irradiated nuclear fuel to obtain uranium and plutonium which are suitable for reuse in fuel fabrication are presented. Nitrate-alkali melts are used for the operation. The experiments are performed on simulators and irradiated samples of BOR-60 fuel in remote-controlled hot boxes.

The coefficients of removal of fission products are presented. A technological scheme, which will shorten the fuel cycle, for purifying hot nuclear fuel is recommended.

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Authors and Affiliations

  1. All-Russia Scientific-Research Institute of Chemical Technology, Russia

    V. T. Gotovchikov, V. I. Makarov, V. T. Orekhov, A. G. Rybakov & V. A. Seredenko

Authors
  1. V. T. Gotovchikov
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  2. V. I. Makarov
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  3. V. T. Orekhov
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  4. A. G. Rybakov
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  5. V. A. Seredenko
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__________

Translated from Atomnaya Energiya, Vol. 99, No. 5, pp. 387–392, November, 2005.

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Gotovchikov, V.T., Makarov, V.I., Orekhov, V.T. et al. Recovery of Uranium and Plutonium from Spent Fuel Elements of Nuclear Reactors. At Energy 99, 823–828 (2005). https://doi.org/10.1007/s10512-006-0023-6

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  • DOI: https://doi.org/10.1007/s10512-006-0023-6

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