Waste loadings of reprocessed spent nuclear fuel vitrified into borosilicate glass can be increased by precipitating environmentally stable phases concentrated with waste components in a chemically stable glass matrix. The principal objective of this thesis was to characterize the development of crystalline powellite (CaMoO4 and related phases) and oxyapatite (Ca2LN8Si6O26) in borosilicate glass-ceramics and to determine how the formation of those phases affected its chemical durability. Borosilicate glasses provided by PNNL were re-melted and quenched at rates from over 300⁰C/s to ~0.05⁰C/s. Isothermal heat treatment experiments were conducted by quenching melts in a molten tin bath at various temperatures, holding for periods of time, and...
Ces travaux proposent une nouvelle approche pour appréhender la durabilité chimique de matrices de c...
A laboratory scale study was carried out on a set of 6 borosilicate waste glasses made from simulate...
Immobilization of high-level and intermediate-level nuclear wastes by vitrification in borosilicate ...
International audienceIn this study, we synthesized glass-ceramics from glasses in the system SiO 2-...
Legacy waste from the decommissioned A-1 nuclear power plant in the Slovak Republic is scheduled for...
AbstractBorosilicate glass-ceramics are being developed to immobilize high-level waste generated by ...
This review summarizes the results of the joint Japanese (Central Research Institute of Electric Pow...
International audienceAll materials can suffer from environmental degradation; the rate and extent o...
Vitrification is currently the most widely used technology for the treatment of high level radioacti...
In order to increase the waste loading efficiency in nuclear waste glasses, alternate glass ceramic ...
Alkali borosilicate glasses have been widely used as an immobilisation network for high level, radio...
International audienceA glass‐ceramic waste form is being developed for immobilization of waste stre...
This thesis investigates the incorporation and solubility of Post Operational Clean-Out (POCO) wast...
Glass corrosion in MCC-1 tests at 90{dollar}\sp\circ{dollar}C and 30{dollar}\sp\circ{dollar}C was ch...
A glass ceramic waste form is being developed for treatment of secondary waste streams generated by ...
Ces travaux proposent une nouvelle approche pour appréhender la durabilité chimique de matrices de c...
A laboratory scale study was carried out on a set of 6 borosilicate waste glasses made from simulate...
Immobilization of high-level and intermediate-level nuclear wastes by vitrification in borosilicate ...
International audienceIn this study, we synthesized glass-ceramics from glasses in the system SiO 2-...
Legacy waste from the decommissioned A-1 nuclear power plant in the Slovak Republic is scheduled for...
AbstractBorosilicate glass-ceramics are being developed to immobilize high-level waste generated by ...
This review summarizes the results of the joint Japanese (Central Research Institute of Electric Pow...
International audienceAll materials can suffer from environmental degradation; the rate and extent o...
Vitrification is currently the most widely used technology for the treatment of high level radioacti...
In order to increase the waste loading efficiency in nuclear waste glasses, alternate glass ceramic ...
Alkali borosilicate glasses have been widely used as an immobilisation network for high level, radio...
International audienceA glass‐ceramic waste form is being developed for immobilization of waste stre...
This thesis investigates the incorporation and solubility of Post Operational Clean-Out (POCO) wast...
Glass corrosion in MCC-1 tests at 90{dollar}\sp\circ{dollar}C and 30{dollar}\sp\circ{dollar}C was ch...
A glass ceramic waste form is being developed for treatment of secondary waste streams generated by ...
Ces travaux proposent une nouvelle approche pour appréhender la durabilité chimique de matrices de c...
A laboratory scale study was carried out on a set of 6 borosilicate waste glasses made from simulate...
Immobilization of high-level and intermediate-level nuclear wastes by vitrification in borosilicate ...