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Characterisation and Durability of a Vitrified Wasteform for Simulated Chrompik III Waste

  • Sam A. Walling
  • , Laura J. Gardner
  • , H. K.Celine Pang
  • , Colleen Mann
  • , Claire L. Corkhill
  • , Alexandra Mikusova
  • , Peter Lichvar
  • , Neil C. Hyatt*
  • *Corresponding author for this work

Research output: Contribution to journalArticle (Academic Journal)peer-review

Abstract

Legacy waste from the decommissioned A-1 nuclear power plant in the Slovak Republic is scheduled for immobilisation within a tailored alkali borosilicate glass formulation, as part of ongoing site cleanup. The aqueous durability and characteri-sation of a simulant glass wasteform for Chrompik III legacy waste, was investigated, including dissolution experiments up to 112 days (90°C, ASTM Type 1 water). The wasteform was an amorphous, light green glassy product, with no observed phase separation or crystalline inclusions. Aqueous leach testing revealed a suitably durable product over the timescale investigated, comparing positively to other simulant nuclear waste glasses and vitreous products tested under similar condi-tions. Iron and titanium rich precipitates were observed to form at the surface of monolithic samples during leaching, with the formation of an alkali deficient alteration layer behind these at later ages. Overall this glass appears to perform well, and in line with expectations for this chemistry, although longer-term testing would be required to predict overall durability. This work will contribute to developing confidence in the disposability of vitrified Chrompik legacy wastes.

Original languageEnglish
Pages (from-to)339-352
Number of pages14
JournalJournal of Nuclear Fuel Cycle and Waste Technology
Volume19
Issue number3
DOIs
Publication statusPublished - 30 Sept 2021

Bibliographical note

Publisher Copyright:
© 2021, Korean Radioactive Waste Society. All rights reserved.

Keywords

  • Characterisation
  • Chrompik
  • Durability
  • Glass
  • Higher activity waste
  • Vitrification

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