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Impurity analysis and dissolution behaviour of plutonium bearing impure MOX scrap: an assessment of recycling feasibility

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Abstract

A significant quantity of plutonium bearing scrap was getting generated during the fabrication of (U,Pu)O2 mixed oxide fuel for Indian Prototype Fast Breeder Reactor. This document assesses the feasibility of carrying out recycling of the impure scrap to permit the efficient plutonium recovery and re-use. The impure scrap which constitutes nearly 5 % of the total throughput was examined for impurities present and dissolution behaviour in HNO3. On the basis of experimental results obtained recycling methodologies are recommended. This study reveals that not all types of the impure scrap need aqueous recycling methods; some can be dry recycled.

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Acknowledgments

The authors are sincerely thankful to colleagues of microwave processing laboratory, CQCS (chemical quality control section) and OFS (oxide fuel section) of AFFF for the cooperation extended during the course of this work.

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Authors and Affiliations

  1. Advanced Fuel Fabrication Facility, Bhabha Atomic Research Centre, Tarapur, 401 502, India

    G. Singh, N. D. Save, R. K. Malav, B. N. Mahanty, D. K. Das, A. K. Mishra, P. G. Behere & Mohd. Afzal

  2. Integrated Fuel Fabrication Facility, Bhabha Atomic Research Centre, Mumbai, 400 085, India

    Pradeep Kumar

  3. Nuclear Fuel Group, Bhabha Atomic Research Centre, Mumbai, 400 085, India

    Arun Kumar

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  1. G. Singh
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  2. Pradeep Kumar
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Correspondence to G. Singh.

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Singh, G., Kumar, P., Save, N.D. et al. Impurity analysis and dissolution behaviour of plutonium bearing impure MOX scrap: an assessment of recycling feasibility. J Radioanal Nucl Chem 309, 1159–1168 (2016). https://doi.org/10.1007/s10967-016-4715-7

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  • DOI: https://doi.org/10.1007/s10967-016-4715-7

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