Surface interfacial analysis of simulant high level nuclear waste glass dissolved in synthetic cement solutions (2022)
Attributed to:
Critical Analysis of Spent Fuel Structure in Radionuclide Release
funded by
EPSRC
Abstract
No abstract provided
Bibliographic Information
Digital Object Identifier: http://dx.doi.org/10.1038/s41529-022-00279-5
Publication URI: http://dx.doi.org/10.1038/s41529-022-00279-5
Type: Journal Article/Review
Parent Publication: npj Materials Degradation
Issue: 1