International perspectives on glass waste form development for low-level and intermediate-level radioactive waste

Международные перспективы разработки стеклообразующих форм для низкоактивных и среднеактивных радиоактивных отходов
John S. McCloy, Brian J. Riley, Malin C. Dixon Wilkins, Jonathan S. Evarts, John Bussey, John D. Vienna, Paul A. Bingham, Daniel J. Gregg, Michael I. Ojovan, Sophie Schuller, Kazuyoshi Uruga, Damien Perret, Élise Régnier, Isabelle Giboire, Wooyong Um, Kai Xu, Ashutosh Goel, Albert A. Kruger
2024-09-24

glass waste formsintermediate-level radioactive wastelow-level radioactive wasteradioactive waste vitrificationthermal treatment processes
The global transition to low-carbon energy sources will require a significant contribution of nuclear energy to achieve emission goals. Low-level radioactive wastes (LLW) and intermediate-level radioactive wastes (ILW) are created in various phases of the nuclear fuel cycle for power generation, as well as from nuclear accidents, legacy weapons production, contaminated site decommissioning, and other nuclear activities such as radiopharmaceutical production. In this review, we will summarize recent developments, state-of-the-art glass formulations, and thermal treatment process developments for vitrification of nuclear LLW and ILW from programs in Europe, Asia, Australia, and North America. Throughout, we will discuss the selection of glass over other possible waste forms and any special processing considerations due to the nature of the waste. The characteristics of the wastes, such as mixed technological waste, waste coming from dismantling of reprocessing facilities, site decommissioning, and accident site decontamination, are important considerations. This is balanced with the suite of technologies available to vitrify these wastes, e.g., variations of incineration, in-can melting, and plasma treatment. Glass properties and microstructural aspects are compared to give an overview of the versatility of packaging matrices, such as homogeneous glasses, composites, and crystalline matrices. The volume and heterogeneity of the waste, specific radionuclide content, and solubility of components in silicate melts, all factor into the selection of a given waste form, processing route, and technology. Case studies include examples from the United States, United Kingdom, the Russian Federation, France, Australia, Japan, Korea, and China.
1
Glass waste forms encompass homogeneous glasses, composites, and crystalline matrices, whose properties and microstructures differ in suitability for radioactive-waste immobilization.
2
International case studies from Europe, Asia, Australia, and North America demonstrate the versatility of glass matrices for wastes from fuel cycles, accidents, decommissioning, weapons production, and radiopharmaceutical activities.
3
The review synthesizes recent glass formulations and thermal-treatment technologies for vitrifying low- and intermediate-level radioactive wastes worldwide.
4
Vitrification approaches include incineration variants, in-can melting, and plasma treatment, each requiring processing adaptations for specific waste types and origins.
5
Waste characteristics—including heterogeneity, volume, radionuclide content, and component solubility—strongly determine the appropriate glass composition, processing route, and vitrification technology.

glass waste forms for vitrification of low-level and intermediate-level radioactive waste

recent developments, glass formulations, thermal treatment processes, and the selection and performance of vitrification matrices for heterogeneous nuclear LLW and ILW

Publication Details
Publication Date
2024-09-24
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Authors
John S. McCloy
Brian J. Riley
Malin C. Dixon Wilkins
Jonathan S. Evarts
John Bussey
John D. Vienna
Paul A. Bingham
Daniel J. Gregg
Michael I. Ojovan
Sophie Schuller
Kazuyoshi Uruga
Damien Perret
Élise Régnier
Isabelle Giboire
Wooyong Um
Kai Xu
Ashutosh Goel
Albert A. Kruger
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