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 |
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Hauptverfasser: | , , , , , , , , , |
Format: | Artikel |
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. |
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ISSN: | 0236-5731 1588-2780 |
DOI: | 10.1007/s10967-016-4715-7 |