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

A significant quantity of plutonium bearing scrap was getting generated during the fabrication of (U,Pu)O 2 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...

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Veröffentlicht in:Journal of radioanalytical and nuclear chemistry 2016-09, Vol.309 (3), p.1159-1168
Hauptverfasser: Singh, G., Kumar, Pradeep, Save, N. D., Malav, R. K., Mahanty, B. N., Das, D. K., Mishra, A. K., Behere, P. G., Afzal, Mohd, Kumar, Arun
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Sprache:eng
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Zusammenfassung:A significant quantity of plutonium bearing scrap was getting generated during the fabrication of (U,Pu)O 2 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 HNO 3 . 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.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-016-4715-7