Thermal Stability of Glass with Simulators of Chloride Highly Radioactive Wastesстатья
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Дата последнего поиска статьи во внешних источниках: 21 февраля 2019 г.
Аннотация:High temperature behavior of sodium–aluminum fluorophosphate glass - a potential matrix for immobilisation of waste salt electrolyte from pyrochemical reprocessing of irradiated nuclear fuel (INF) has been studied. The glass crystallizes with formation of phosphate phases, which dissolve above 640 C, leading to homogenisation of the glass. Similar transformation of the glass matrix from the decay of short-lived fission products may have a negative effect on properties
of vitrified radioactive chloride wastes during their storage in a repository.