Matrices for radioactive waste immobilization: a review

Pilania, Ritu Kumari; Dube, Charu Lata

doi:10.3389/fmats.2023.1236470

Cited by 6 publications

(1 citation statement)

References 126 publications

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“…The chemical composition of glass, the additive introduced, and the method of its preparation determine its use. Therefore, glass-based materials are used in fiber optics [9], as radioactive waste immobilizers [10], as bioactive materials [11], or glazes [12]. Due to all the above qualities, Pr 3+ ions are preferable for introducing them into a stable matrix.…”

Section: Introductionmentioning

confidence: 99%

UVC Up-Conversion and Vis-NIR Luminescence Examined in SrO-CaO-MgO-SiO2 Glasses Doped with Pr3+

Bezkrovna,

Lisiecki,

Macalik

et al. 2024

Materials

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The application of ultraviolet-C light in the field of surface treatment or photodynamic therapy is highly prospective. In this regard, the stable fluorescent silicate SrO-CaO-MgO-SiO2-Pr2O3 glasses able to effectively convert visible excitation on the ultraviolet praseodymium emission were fabricated and examined. An unusual wide-range visible-to-UVC up-conversion within 240–410 nm has been achieved in Pr3+-doped glasses, revealing their potential advantage in different sophisticated disinfection technologies. The integrated emission intensity was studied as a function of light excitation power to assess a mechanism attributed to UVC luminescence. Especially, it was revealed that the multicomponent silicate glass qualities and praseodymium 3PJ excited state peculiarities are favorable to obtaining useful broadband ultraviolet up-converted luminescence. The glass dispersion qualities were determined between 450–2300 nm. The impact of praseodymium concentration on Vis-NIR spectroscopic glass qualities was evaluated employing absorption spectra, emission spectra, and decay curves of luminescence associated with two involved praseodymium excited states. Especially, efficient interionic interactions can be inferred by investigating the decrease in 1D2 state experimental lifetime in the heavily doped samples. Examination of absorption spectra as a function of temperature implied that excitation at 445 nm should be quite effective up to T = 625 K. Contrary to this, temperature elevation gives rise to a moderate lowering of the visible praseodymium luminescence.

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Section: Introductionmentioning

confidence: 99%

UVC Up-Conversion and Vis-NIR Luminescence Examined in SrO-CaO-MgO-SiO2 Glasses Doped with Pr3+

Bezkrovna,

Lisiecki,

Macalik

et al. 2024

Materials

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Vitrification as a Key Solution for Immobilisation Within Nuclear Waste Management

Ojovan

2024

Arab J Sci Eng

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Vitreous materials in the form of both relatively homogeneous glasses and composite glass crystalline materials (GCM) incorporating disperse crystalline phases are currently the most reliable wasteforms effectively used on industrial scale for nuclear waste immobilisation. Glasses are stable solid-state materials with a topologically disordered atomic structure in the form of solid solutions, i.e. solutions frozen via vitrification to a solid state without forming regular crystalline phases. Nuclear waste vitrification is attractive because of technological and compositional flexibility enabling hazardous elements to be safely immobilised and providing a glassy material characterised by high corrosion resistance, mechanical and radiation durability, as well as effectively reducing the volume of the resulting wasteform.

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A reusable graphene oxide aerogel for pre-concentrating and recovering uranium from water and valorisation of spent material in a cementitious material

Gandhi,

Naga Jyothi,

Gomosta

et al. 2024

Journal of Cleaner Production

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Matrices for radioactive waste immobilization: a review

Cited by 6 publications

References 126 publications

UVC Up-Conversion and Vis-NIR Luminescence Examined in SrO-CaO-MgO-SiO2 Glasses Doped with Pr3+

UVC Up-Conversion and Vis-NIR Luminescence Examined in SrO-CaO-MgO-SiO2 Glasses Doped with Pr3+

Vitrification as a Key Solution for Immobilisation Within Nuclear Waste Management

A reusable graphene oxide aerogel for pre-concentrating and recovering uranium from water and valorisation of spent material in a cementitious material

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