Publication | Closed Access
Vapor hydration of a simulated borosilicate nuclear waste glass in unsaturated conditions at 50 °C and 90 °C
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Citations
52
References
2015
Year
Nuclear Waste ManagementEngineeringVitrificationWaste TreatmentComplete SaturationWaste DisposalGlass MaterialGlass-ceramicChemical EngineeringTransport PhenomenaWater TreatmentNuclear MaterialsThermodynamicsNuclear ReactorsMaterials ScienceVapor HydrationWaste ManagementRadioactive Waste DisposalRepository ConditionsEnvironmental EngineeringDewvaporationRecyclingUnsaturated Conditions
Vapor hydration of a simulated typical French nuclear intermediate-level waste (ILW) glass in unsaturated conditions has been studied in order to simulate its behaviour under repository conditions before complete saturation of the disposal site.
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