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Characterisation and disposability assessment of multi-waste stream in-container vitrified products for higher activity radioactive waste

DOI: 10.1016/j.jhazmat.2020.123764 DOI Help

Authors: Sam A. Walling (The University of Sheffield) , Marcus N. Kauffmann (The University of Sheffield) , Laura J. Gardner (University of Sheffield) , Daniel J. Bailey (The University of Sheffield) , Martin C. Stennett (The University of Sheffield) , Claire L. Corkhill (The University of Sheffield) , Neil C. Hyatt (The University of Sheffield)
Co-authored by industrial partner: No

Type: Journal Paper
Journal: Journal Of Hazardous Materials

State: Published (Approved)
Published: August 2020

Open Access Open Access

Abstract: Materials from GeoMelt® In-Container Vitrification (ICV)™ of simulant UK nuclear wastes were characterised to understand the partitioning of elements, including inactive surrogates for radionuclide species of interest, within the heterogeneous products. Aqueous durability analysis was performed to assess the potential disposability of the resulting wasteforms. The vitrification trial aimed to immobilise a variety of simulant legacy waste streams representative of decommissioning operations in the UK, including plutonium contaminated material, Magnox sludges and ion-exchange materials, which were vitrified upon the addition of glass forming additives. Two trials with different wastes were characterised, with the resultant vitreous wasteforms comprising olivine and pyroxene crystalline minerals within glassy matrices. Plutonium surrogate elements were immobilised within the glassy fraction rather than partitioning into crystalline phases. All vitrified products exhibited comparable or improved durability to existing UK high level waste vitrified nuclear wasteforms over a 28 day period.

Journal Keywords: Thermal treatment; durability; glass; immobilization; nuclear

Subject Areas: Materials


Instruments: B18-Core EXAFS

Documents:
1-s2.0-S0304389420317532-main.pdf

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