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Processes for preparing mixed oxides, as applied to conditions of spent nuclear fuel reprocessing without complete separation of U and Pu

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Radiochemistry Aims and scope

Abstract

Technologies for spent nuclear fuel reprocessing and fabrication of new fuel without complete separation of Pu from U meet the requirements of nonproliferation of nuclear weapons and allow the number of process operations to be reduced. Three types of known processes for converting a joint solution to mixed plutonium and uranium oxides are considered in a brief literature review: “direct“ thermal denitration without isolation of intermediates, thermal denitration with conversion of nitrates to oxides in several steps, and isolation of intermediates with their separation from solution in the first step, followed by their heat treatment. It is advisable to combine processes for preparation of single-phase mixed U-Pu oxides with their purification. Additional experimental data on coprecipitation of uranyl and plutonyl oxalates in oxidizing medium are presented.

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Authors and Affiliations

  1. Khlopin Radium Institute, Research and Production Association, Federal State Unitary Enterprise, 2-i Murinskii pr. 28, St. Petersburg, 194021, Russia

    D. N. Bykhovskii, M. A. Kuz’mina & G. S. Novikov

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  1. D. N. Bykhovskii
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  2. M. A. Kuz’mina
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  3. G. S. Novikov
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Correspondence to D. N. Bykhovskii.

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Original Russian Text © D.N. Bykhovskii, M.A. Kuz’mina, G.S. Novikov, 2010, published in Radiokhimiya, 2010, Vol. 52, No. 2, pp. 111–115.

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Bykhovskii, D.N., Kuz’mina, M.A. & Novikov, G.S. Processes for preparing mixed oxides, as applied to conditions of spent nuclear fuel reprocessing without complete separation of U and Pu. Radiochemistry 52, 127–132 (2010). https://doi.org/10.1134/S1066362210020025

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  • DOI: https://doi.org/10.1134/S1066362210020025

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