Dear Colleagues,
Searching for routes of optimal waste management with or without their further reuse is an important aspect of the current stage of civilisation development and progress. Non-radioactive waste streams can be transformed into an inert form via contaminants binding or encapsulation. Such stabilisation reduces the potential hazard of toxic waste components by converting contaminants into insoluble forms. This can be done using durable solids of high structural integrity. Waste processing technologies which produce durable materials with a minimal ecological impact are preferred among affordable options. Inertisation provides minimal environmental impact of materials and therefore is a key technological component both for any reusage and/or disposal of waste materials. In contrast to non-radioactive waste the nuclear waste is associated with intrinsic harmful radiations and if not cleared from regulatory control for its negligible hazard is always intended to disposal which is considered as the end point of nuclear waste management. Technologies which effectively immobilise toxic waste components and radionuclides are hence most appreciated. With many research programmes under way this Topical Collections invites contributing articles and Encyclopedia entries reporting on current advances and perspectives in utilisation of vitreous and glass-based materials, especially accounting for their applications in circular economy including hazardous waste processing as well as nuclear waste immobilisation. All aspects of materials synthesis and structural and property investigation are welcome with focus on utilisation of materials in practical applications.
Prof. Dr. Michael Ojovan
Prof. Dr. Kai Xu
Collection Editors
Institution: School of Chemical, Materials and Biological Engineering, The University of Sheffield, Sheffield S1 3JD, UK and State Key Laboratory of Silicate Materials for Architectures, Wuhan University of Technology, Wuhan, China
Interests: radioactive waste, glass transition; glass corrosion; viscosity; vitrification; nuclear waste; immobilisation; radiation effects
Institution: State Key Laboratory of Silicate Materials for Architectures, Wuhan University of Technology, Wuhan, China
Interests: glasses; glass–ceramics; hazardous and nuclear waste vitrification; numerical simulation of melter
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