Funder: FfWGFunder: Cambridge Philosophical SocietyAbstract: The aim of this paper was to assess factors affecting primary and secondary phase separation in simplified calcium borosilicate glasses studied for nuclear waste applications. Several glasses with varying [MoO3] and [B2O3] were synthesized and exposed to Au‐irradiation to examine compositional effects on glass structure and domain size of separated phases induced by accumulated radiation damage resulting from α‐decay over a ~1000 year timeframe. The produced glasses fell within the immiscibility dome of CaO−SiO2−B2O3 and showed a unique microstructure of embedded immiscibility with three identifiable amorphous phases according to electron microscopy, Raman spectroscopy, and diffra...
Alkali borosilicate glasses have been widely used as a matrix for the vitrification of high level ra...
International audienceBorosilicate glasses are considered for the long-term confinement of high-leve...
The United States department of energy (DOE) has proposed an alkali alkaline-earth aluminoborosilica...
The aim of this paper was to assess factors affecting primary and secondary phase separation in simp...
Borosilicate glasses for nuclear waste applications are limited in waste loading by the precipitatio...
International audienceA series of calcium borosilicate glasses with varying [B2O3], [MoO3], and [CaO...
This is the final version of the article. It first appeared from Royal Society of Chemistry via http...
Molybdenum solubility is a limiting factor to actinide loading in nuclear waste glasses, as it initi...
In order to increase the waste loading efficiency in nuclear waste glasses, alternate glass ceramic ...
Assessing the behavior under irradiation of oxide glasses used for nuclear waste immobilization is e...
MoO 3 is one of the challenging oxides in nuclear waste vitrification in the UK. It has a poor solu...
Glasses used for nuclear waste immobilization are subjected to high levels of radiation, and this ma...
International audienceAs borosilicate glasses are used in many countries to immobilize fission produ...
Alkali borosilicate glasses have been widely used as a matrix for the vitrification of high level ra...
International audienceBorosilicate glasses are considered for the long-term confinement of high-leve...
The United States department of energy (DOE) has proposed an alkali alkaline-earth aluminoborosilica...
The aim of this paper was to assess factors affecting primary and secondary phase separation in simp...
Borosilicate glasses for nuclear waste applications are limited in waste loading by the precipitatio...
International audienceA series of calcium borosilicate glasses with varying [B2O3], [MoO3], and [CaO...
This is the final version of the article. It first appeared from Royal Society of Chemistry via http...
Molybdenum solubility is a limiting factor to actinide loading in nuclear waste glasses, as it initi...
In order to increase the waste loading efficiency in nuclear waste glasses, alternate glass ceramic ...
Assessing the behavior under irradiation of oxide glasses used for nuclear waste immobilization is e...
MoO 3 is one of the challenging oxides in nuclear waste vitrification in the UK. It has a poor solu...
Glasses used for nuclear waste immobilization are subjected to high levels of radiation, and this ma...
International audienceAs borosilicate glasses are used in many countries to immobilize fission produ...
Alkali borosilicate glasses have been widely used as a matrix for the vitrification of high level ra...
International audienceBorosilicate glasses are considered for the long-term confinement of high-leve...
The United States department of energy (DOE) has proposed an alkali alkaline-earth aluminoborosilica...