Characterisation and disposability assessment of multi-waste stream in-container vitrified products for higher activity radioactive waste.
Durability
Glass
Immobilization
Nuclear
Thermal treatment
Journal
Journal of hazardous materials
ISSN: 1873-3336
Titre abrégé: J Hazard Mater
Pays: Netherlands
ID NLM: 9422688
Informations de publication
Date de publication:
05 01 2021
05 01 2021
Historique:
received:
23
04
2020
revised:
28
07
2020
accepted:
19
08
2020
entrez:
29
10
2020
pubmed:
30
10
2020
medline:
30
10
2020
Statut:
ppublish
Résumé
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.
Identifiants
pubmed: 33113733
pii: S0304-3894(20)31753-2
doi: 10.1016/j.jhazmat.2020.123764
pii:
doi:
Types de publication
Journal Article
Research Support, Non-U.S. Gov't
Langues
eng
Sous-ensembles de citation
IM
Pagination
123764Informations de copyright
Copyright © 2020 The Authors. Published by Elsevier B.V. All rights reserved.