Waste forms for actinides: borosilicate glasses
Bernd Grambow

TL;DR
This paper discusses the development and analysis of borosilicate glass matrices for immobilizing actinide-containing nuclear waste, emphasizing long-term stability, corrosion resistance, and safety in geological disposal.
Contribution
It provides insights into the properties, corrosion behavior, and long-term performance of borosilicate glasses for nuclear waste immobilization.
Findings
Borosilicate glasses effectively contain actinides for long-term disposal.
Corrosion processes form secondary phases that immobilize radionuclides.
Glass stability and secondary phase formation are key to safety.
Abstract
This high level liquid radioactive reprocessing waste will become vitrified in order to obtain a stable borosilicate waste glass matrix that provides protection against environmental dispersion. Since vitrified waste is in a solid form, transportation, storage and final geological disposal are facilitated. The glass products contain the non-extracted fraction of uranium and plutonium together with the minor actinides Am, Np and Cm and fission products such as (90Sr, 99Tc ou 137Cs). In the long term, the safest way to deal with actinide containing nuclear waste (vitrified waste or spent fuel) is geological disposal. The disposal locations are isolated from biosphere by engineered barriers while dense rock characteristics and low groundwater flow assure that any potential return of radionuclides to biosphere by groundwater transport will be retarded for many hundreds of thousands of…
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Taxonomy
TopicsNuclear materials and radiation effects · Radioactive element chemistry and processing · Nuclear Materials and Properties
