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Advanced Vitreous Wasteforms for Radioactive Salt Cake Waste Immobilisation

Published online by Cambridge University Press:  24 January 2020

Vladimir A. Kashcheev ,
Nikolay D. Musatov  and
Michael I. Ojovan Open the ORCID record for Michael I. Ojovan [Opens in a new window]
Vladimir A. Kashcheev
Affiliation:
A.A. Bochvar High-technology Research Institute of Inorganic Materials (VNIINM), Moscow, Russia
Nikolay D. Musatov
Affiliation:
A.A. Bochvar High-technology Research Institute of Inorganic Materials (VNIINM), Moscow, Russia
Michael I. Ojovan*
Affiliation:
M.V. Lomonosov Moscow State University, Radiochemistry Department, Moscow, Russia
*
*(Email: M.I.Ojovan@gmail.com)
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Abstract

Salt cake radioactive waste is a remnant solid salt concentrate after deep evaporation of radioactive evaporator concentrate at WWER NPP’s. The traditional cementing of borate-containing liquid radioactive waste, to which the salt cake belongs, leads to a significant increase in the volume of the final product. This work describes borosilicate vitreous wasteforms developed to immobilize radioactive salt cake waste and comprises data on both glass synthesis and characterization. The composition of glass selected for the purpose of immobilisation of the salt cake radioactive waste allows to include up to 40 wt. % of the oxides contained in the salt cake and to reduce the volume of the final product by more than 2 times compared with the cement compound. The batches were melted in a cold crucible melter at 1200 °C. The normalized cesium leaching rate of the vitrified wasteform product was within range 3.0·10-5 – 3.7·10-6 g/(cm2·day).

Keywords

glassnuclear materialswaste managementenvironmentally protective
Type
Articles
Information
MRS Advances , Volume 5 , Issue 3-4: Scientific Basis for Nuclear Waste Management XLIII , 2020 , pp. 121 - 129
Copyright
Copyright © Materials Research Society 2020

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