Research on vitrification technology to immobilize radioactive sludge generated from Fukushima Daiichi power plant: enhanced glass medium

Amamoto, Ippei; Kobayashi, Hidekazu; Kitamura, Naoto; Takebe, Hiromichi; Mitamura, Naoki; Tsuzuki, Toshio; Fukayama, Daigen; Nagano, Yasuo; Jantzen, T.; Hack, Klaus

doi:10.1080/00223131.2015.1136579

Cited by 6 publications

(4 citation statements)

References 16 publications

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“…For the development of the system for aircooling the nuclear fuel during the accident like FDNPP, numerical study was carried out [22]. For the waste management, estimation of the inventory [23], vitrification for the immobilization of radioactive sludge generated from FDNPP [24], treatment of radioactive Cs by cobalt ferrocyanide microparticles [25], treatment of radioactive-waste-seawater [26] and U separation from a simulant fuel debris [27] were reported. Interestingly, two reviews on the effects of radiation damage on spent fuel (SF) for direct disposal [28,29] were reported.…”

Section: Editorial Summarymentioning

confidence: 99%

Summary report of recent activities for decontamination and environmental restoration after Fukushima Daiichi nuclear power plant accident

Ohnuki

2018

Journal of Nuclear Science and Technology

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Section: Editorial Summarymentioning

confidence: 99%

Summary report of recent activities for decontamination and environmental restoration after Fukushima Daiichi nuclear power plant accident

Ohnuki

2018

Journal of Nuclear Science and Technology

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“…Iron phosphate glass (IPG) has attracted a lot of research interest from glass scientists due to its superior properties that project it as a next generation material for vitrification of high-level radioactive waste from fast reactors. − Also recently, its application as an anode material in batteries was also investigated . Iron phosphate glass optical fibers have also shown good mechanical properties, and recently, iron-containing phosphate glass fibers are also studied for slow-release fertilizers .…”

Section: Introductionmentioning

confidence: 99%

Toward Atomistic Understanding of Iron Phosphate Glass: A First-Principles-Based Density Functional Theory Modeling and Study of Its Physical Properties

Singh,

Dholakia,

Chandra

2024

J. Phys. Chem. B

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Iron phosphate glasses (IPGs) have been proposed as futuristic materials for nuclear waste immobilization and anode materials for lithium batteries. Recently, many attempts have been made to propose atomistic models of IPGs to explain their properties from an atomistic viewpoint. In this paper, we seek to produce small scale models of IPG that can be handled within the scheme of density functional theory (DFT) to study its electronic structure. The starting models, generated using the Monte Carlo (MC) method, were subsequently annealed using ab initio molecular dynamics (AIMD) to minimize the coordination defects. The geometry of the equilibrated structure was then optimized at 0 K. This hybrid approach (MC + AIMD + DFT optimization) produced good atomistic models of IPG, which can reproduce the experimentally observed band gap, vibrational density of states, magnetic moment of Fe, and mechanical and optical properties. Computationally expensive melt-quench simulation can be avoided using the present approach, allowing the use of DFT for accurate calculations of properties.

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“…Similar sludges are also abundant at the Hanford sites in the USA, and both glass and ceramic waste forms have been developed to immobilize sludges alone [7][8][9]. In addition, many studies have focused on the thermal treatment of other types of radioactive sludge, such as Magnox sludge [10,11] and Fukushima sludge [12], to form glass or ceramic wasteforms.…”

Section: Introductionmentioning

confidence: 99%

Influence of Radioactive Sludge Content on Vitrification of High-Level Liquid Waste

et al. 2023

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The radioactive sludges formed at the bottom of high-level liquid waste (HLW) storage tanks pose challenges when the HLWs are vitrified. This study aims to determine the influence of the sludge content (enriched in Na2O, Al2O3, NiO, Fe2O3, and BaSO4) on the structure and properties of waste glasses in order to find the optimal ratio of sludges to HLW during vitrification. In the experiments, the simulated sludge and simulated HLW were mixed at different ratios from 0:8 to 4:4, with an overall waste content of 16 wt %, in a borosilicate glass wasteform. It is found that the glass density, molar volume, sulfur retention, and glass transition temperature changed little when increasing the sludge content of the glasses, while the viscosity, chemical durability, and crystallization features of the glasses varied notably. The crystals formed in the glasses during the thermal treatment were exclusively Fe-substituted diopside (Ca, Mg, Fe)2Si2O6. An increase in the Al2O3 and NiO content of the glasses may have been responsible for the increased crystallinity at high temperatures. The leaching rate of Si, B, Na, and Cs from the glasses declined with the increasing addition of sludge to the glasses. Although all the glasses fulfilled the requirements for vitrification processing and glass-product performance, it is recommended that the sludge content of the whole waste should not exceed 25 wt %. This study guides further research on the immobilization of high-level sludges.

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Research on vitrification technology to immobilize radioactive sludge generated from Fukushima Daiichi power plant: enhanced glass medium

Cited by 6 publications

References 16 publications

Summary report of recent activities for decontamination and environmental restoration after Fukushima Daiichi nuclear power plant accident

Summary report of recent activities for decontamination and environmental restoration after Fukushima Daiichi nuclear power plant accident

Toward Atomistic Understanding of Iron Phosphate Glass: A First-Principles-Based Density Functional Theory Modeling and Study of Its Physical Properties

Influence of Radioactive Sludge Content on Vitrification of High-Level Liquid Waste

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