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Evolution of cations speciation during the initial leaching stage of alkali-borosilicate-glasses

Published online by Cambridge University Press:  27 January 2020

Osama M. Farid ,
M.I. Ojovan  and
R.O. Abdel Rahman Open the ORCID record for R.O. Abdel Rahman [Opens in a new window]
Osama M. Farid
Affiliation:
Reactors Department, Nuclear Research Center, Atomic Energy Authority of Egypt, P.O. 13759, Inshas, Cairo, Egypt; usamafa98@hotmail.co.uk
M.I. Ojovan
Affiliation:
Department of Materials Science and Engineering, The University of Sheffield, UK; m.ojovan@sheffield.ac.uk
R.O. Abdel Rahman*
Affiliation:
Hot Laboratory Center, Atomic Energy Authority of Egypt, P.O. 13759, Inshas, Cairo, Egypt; alaarehab@yahoo.com
*
*(Email: alaarehab@yahoo.com)
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Abstract

Alkali-borosilicate glasses (ABS) are used as host immobilization matrices for different radioactive waste streams and are characterized by their ability to incorporate a wide variety of metal oxides with respectively high waste loadings. The vitreous wasteform is also characterized by very good physical and chemical durability. The durability of three ABS compositions were analyzed by investigating their leaching behavior using the MCC1 test protocol and these data were used to investigate the waste components retention in the altered layer and the evolution of the interfacial water composition during the test. The results indicated that the Mg species evolution is exceptional with respect to other alkaline elements and dependent on glass matrix composition and leaching progress, while transition elements speciation is fairly constant throughout leaching process and independent on glass compositions. Si and B species are changing during leaching process and are affected by waste composition. For modified wasteform sample, evolution of Mg, Si and B species is respectively constant, whereas at highest waste loading, these elements have fairly constant speciation evolution within the first 2 weeks of leaching.

Keywords

waste managementglass
Type
Articles
Information
MRS Advances , Volume 5 , Issue 3-4: Scientific Basis for Nuclear Waste Management XLIII , 2020 , pp. 185 - 193
Copyright
Copyright © Materials Research Society 2020

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