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Radiolysis and Ageing of C2-BTP in Cinnamaldehyde/Hexanol Mixtures

Published online by Cambridge University Press:  19 October 2011

Anna Fermvik
Affiliation:
anna.fermvik@chalmers.se, Chalmers University of Technology, Nuclear Chemistry, Kemiv. 4, Gothenburg, SE-412 96, Sweden
Christian Ekberg
Affiliation:
che@chalmers.se, Chalmers University of Technology, Nuclear Chemistry, Kemiv. 4, Gothenburg, SE-412 96, Sweden
Teodora Retegan
Affiliation:
tretegan@chalmers.se, Chalmers University of Technology, Nuclear Chemistry, Kemiv. 4, Gothenburg, SE-412 96, Sweden
Gunnar Skarnemark
Affiliation:
gunnar.skarnemark@chalmers.se, Chalmers University of Technology, Nuclear Chemistry, Kemiv. 4, Gothenburg, SE-412 96, Sweden
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Abstract

The separation of actinides from lanthanides is an important step in the alternative methods for nuclear waste treatment currently under development. Polycyclic molecules containing nitrogen are synthesised and used for solvent extraction. A potential problem in the separation process is the degradation of the molecule due to irradiation or ageing. An addition of nitrobenzene has proved to have an inhibitory effect on degradation when added to a system containing C2-BTP in hexanol before irradiation. In this study, 2,6 di(5,6 diethyl 1,2,4 triazin 3 yl)pyridine (C2-BTP) was dissolved in different mixtures of cinnamaldehyde and hexanol and the effects on extraction after ageing and irradiation were investigated. Similar to nitrobenzene, cinnamaldehyde contains an aromatic ring which generally has a relatively high resistance towards radiolysis. Both C2-BTP in cinnamaldehyde and C2-BTP in hexanol seem to degrade with time. The system with C2-BTP in pure hexanol is relatively stable up to 17 days but then starts slowly to degrade. The solution with pure cinnamaldehyde as diluent started to degrade after only ∼20 hours. The opposite is true for degradation caused by radiolysis; hexanol systems are more sensitive to radiolysis than cinnamaldehyde systems. Most of the radiolytic degradation took place during the first days of irradiation, up to a dose of 4 kGy.

Type
Research Article
Copyright
Copyright © Materials Research Society 2007

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