Separation of fission produced (106)Ru from simulated high level nuclear wastes for production of brachytherapy sources

An effective and simple process for the isolation of (106)Ru from high-level liquid wastes was developed. Radioactive ruthenium was oxidized by H(5)IO(6) in HNO(3) solution and was extracted to CCl(4) phase in the form of RuO(4). In order to obtain ruthenium in the suitable form for production of br...

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Autores principales: Blicharska, Magdalena, Bartoś, Barbara, Krajewski, Seweryn, Bilewicz, Aleksander
Formato: Online Artículo Texto
Lenguaje:English
Publicado: Springer Netherlands 2013
Materias:
Article
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC4514637/
https://www.ncbi.nlm.nih.gov/pubmed/26224947
http://dx.doi.org/10.1007/s10967-013-2570-3
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author Blicharska, Magdalena
Bartoś, Barbara
Krajewski, Seweryn
Bilewicz, Aleksander
author_facet Blicharska, Magdalena
Bartoś, Barbara
Krajewski, Seweryn
Bilewicz, Aleksander
author_sort Blicharska, Magdalena
collection PubMed
description An effective and simple process for the isolation of (106)Ru from high-level liquid wastes was developed. Radioactive ruthenium was oxidized by H(5)IO(6) in HNO(3) solution and was extracted to CCl(4) phase in the form of RuO(4). In order to obtain ruthenium in the suitable form for production of brachytherapy sources, RuO(4) in organic phase was reduced and re-extracted to aqueous phase. The efficiency of extraction of (103)Ru to organic phase was 86 %, re-extraction to aqueous solution was near 100 %, so the overall recovery of (103)Ru is estimated at more than 80 %.
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spelling pubmed-45146372015-07-27 Separation of fission produced (106)Ru from simulated high level nuclear wastes for production of brachytherapy sources Blicharska, Magdalena Bartoś, Barbara Krajewski, Seweryn Bilewicz, Aleksander J Radioanal Nucl Chem Article An effective and simple process for the isolation of (106)Ru from high-level liquid wastes was developed. Radioactive ruthenium was oxidized by H(5)IO(6) in HNO(3) solution and was extracted to CCl(4) phase in the form of RuO(4). In order to obtain ruthenium in the suitable form for production of brachytherapy sources, RuO(4) in organic phase was reduced and re-extracted to aqueous phase. The efficiency of extraction of (103)Ru to organic phase was 86 %, re-extraction to aqueous solution was near 100 %, so the overall recovery of (103)Ru is estimated at more than 80 %. Springer Netherlands 2013-06-20 2013 /pmc/articles/PMC4514637/ /pubmed/26224947 http://dx.doi.org/10.1007/s10967-013-2570-3 Text en © The Author(s) 2013 https://creativecommons.org/licenses/by/2.0/ Open AccessThis article is distributed under the terms of the Creative Commons Attribution License which permits any use, distribution, and reproduction in any medium, provided the original author(s) and the source are credited.
spellingShingle Article
Blicharska, Magdalena
Bartoś, Barbara
Krajewski, Seweryn
Bilewicz, Aleksander
Separation of fission produced (106)Ru from simulated high level nuclear wastes for production of brachytherapy sources
title Separation of fission produced (106)Ru from simulated high level nuclear wastes for production of brachytherapy sources
title_full Separation of fission produced (106)Ru from simulated high level nuclear wastes for production of brachytherapy sources
title_fullStr Separation of fission produced (106)Ru from simulated high level nuclear wastes for production of brachytherapy sources
title_full_unstemmed Separation of fission produced (106)Ru from simulated high level nuclear wastes for production of brachytherapy sources
title_short Separation of fission produced (106)Ru from simulated high level nuclear wastes for production of brachytherapy sources
title_sort separation of fission produced (106)ru from simulated high level nuclear wastes for production of brachytherapy sources
topic Article
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC4514637/
https://www.ncbi.nlm.nih.gov/pubmed/26224947
http://dx.doi.org/10.1007/s10967-013-2570-3
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