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
Format:	Artikel
Sprache:	eng
Schlagworte:	Analysis Breeder reactors Chemistry Chemistry and Materials Science Diagnostic Radiology Dissolution Fast breeder Feasibility studies Hadrons Heavy Ions Inorganic Chemistry MOX Nuclear Chemistry Nuclear energy Nuclear fuels Nuclear industry Nuclear Physics Physical Chemistry Plutonium Recycling Scrap Waste management
Online-Zugang:	Volltext
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