Physico-chemical properties of γ-irradiated International Simple Glass (ISG) nuclear waste simulants with low levels of iron impurities

Jiménez, José A.; Crawford, Charles L.; Lascola, Robert; Christian, Jonathan H.; Foley, Bryan J.

doi:10.1016/j.chphi.2023.100233

Cited by 3 publications

(1 citation statement)

References 31 publications

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“…68 This effect is not seen in low Fe-content alkali-borosilicate glasses, but the results that Jiménez et al obtained after 0.95 MGy γ-irradiation of ISG nuclear waste, glass simulants with low Fe content indicated no significant changes in structural, chemical, and thermal properties. 69 On the other hand, Zhang et al showed that when exposed to γ-radiation, borosilicate glasses remain stable up to absorbed doses of 800 kGy, but at higher doses, structural changes occur as a result of bond ruptures and surface particle release. In their case, they observed the release of Na, O, and B, but the type of particles released depends on the glass composition.…”

Section: Fig 2 -Kinetics Of Glass Corrosion Process 50mentioning

confidence: 99%

Nuclear Waste Management

Cetina

2024

Kem. ind. (Online)

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Nuclear energy production generates nuclear waste. Nuclear and radioactive waste, especially high level waste (HLW) and intermediate level waste (ILW), require special long-term safe management solutions. One part of the solution involves recycling through reprocessing of spent nuclear fuel. Recycling reduces the volume of nuclear waste and allows for the reuse of some of its components. This can be achieved through methods such as adsorption, ion exchange, coagulation, flotation, filtration, chemical precipitation, reverse osmosis, and solvent extraction, like the PUREX process. Another possible future solution involves partitioning and transmutation technology, which can reduce the production of nuclear waste. The best long-term solution is the immobilisation of HLW and ILW in a solid matrix. Materials used for this purpose include glasses, cements, bitumen, geopolymers, concrete, and ceramics as a promising material. While cementation is still the most commonly used immobilisation method due to its low cost and simplicity, vitrification is a more permanent long-term solution. Deep geological disposal in combination with vitrification and a robust multi-barrier system is considered the most acceptable solution for safe nuclear waste isolation. This review provides insight into the mostly commonly used and promising immobilisation materials, as well as the most effective methods and technologies currently in use and under development for the management of HLW and ILW in nuclear waste management.

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Section: Fig 2 -Kinetics Of Glass Corrosion Process 50mentioning

confidence: 99%