Vitrification of Combustible Dry Active Waste Generated from Korean Nuclear Power Plants

Song, Myung‐Jae; Kim, Cheon-Woo

doi:10.5453/jhps.39.250

Cited by 4 publications

(3 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…However, radionuclides become chemically very stable by ionic bonding with oxygen in the empty space between the glass structures. This indicates the nuclides never escape even if the glass breaks and shatters (Song, 2020), (Song & Kim, 2004).…”

Section: Vitrification Processmentioning

confidence: 99%

Future Plans About the High-Level Radioactive Waste Disposal

Hong¹,

Thompson²

2022

J Stud Res

View full text Add to dashboard Cite

The Biden Administration officially advocated nuclear energy to successfully achieve a net-zero carbon economy for America by 2050. South Korea also abolished the ‘nuclear power phase-out’ policy’, promoting the expansion of nuclear power because of its high efficiency. Despite the preference for utilizing nuclear energy is growing, limitations on expanding the use of nuclear power and insisting on it as a solution for future energy shortages currently exist because there are no effective treatments for the ‘high-level radioactive waste’ other than accumulating in the reactor. Thus, to find effective treatment technology, I reviewed ‘pyroprocessing’ and ‘vitrification’ as possible technologies to solve the nuclear waste problem. I deeply searched the process, advantages, problems, and prospects of the two technologies based on research papers and the ‘Korean Nuclear Energy Newspaper’, and organized them in a table. As a result, I derived an ideal high-level radioactive waste treatment method and predicted that the outlook for nuclear energy will be positive.

show abstract

Section: Vitrification Processmentioning

confidence: 99%

Future Plans About the High-Level Radioactive Waste Disposal

Hong¹,

Thompson²

2022

J Stud Res

View full text Add to dashboard Cite

show abstract

“…For example, the United States vitrifies low‐activity liquid waste with a Joule heating ceramic melter at the Hanford site 9–12 . South Korea has applied cold crucible induction melters to treat dry waste generated from nuclear power plants, such as work clothes, plastics, and paper 13,14 . In China, thermal plasma technology is used to gasify dry waste and vitrify residual ash into glass waste form 15 …”

Section: Introductionmentioning

confidence: 99%

“…[9][10][11][12] South Korea has applied cold crucible induction melters to treat dry waste generated from nuclear power plants, such as work clothes, plastics, and paper. 13,14 In China, thermal plasma technology is used to gasify dry waste and vitrify residual ash into glass waste form. 15 Pb and Bi are the main components of heavy metal oxide glass.…”

Section: Introductionmentioning

confidence: 99%

Vitrification of lead–bismuth alloy nuclear waste into a glass waste form

Zhou,

Niu,

et al. 2024

Int J of Appl Glass Sci

View full text Add to dashboard Cite

Lead–bismuth eutectic (LBE), a promising coolant in advanced nuclear systems, can be activated by neutrons during nuclear reactor operations. The decommissioning of nuclear facilities would generate lead–bismuth (Pb–Bi) alloy‐contaminated nuclear waste. The current metallic nuclear waste treatment approach involves remelting followed by cementitious solidification. This increases the waste volume and the risk of radionuclide migration in groundwater. Therefore, this study developed a method for vitrification of Pb–Bi alloy waste. Different amounts of SiO2 were added at 750–1100°C in the air to turn the simulated LBE waste into glass waste form. The values of the normalized elemental leaching rates (Pb, Bi, Si, Te, and Ni) determined using the 28‐day static leaching test were less than .2 g m−2 d−1 and varied with SiO2 addition. Furthermore, a three‐stage evolution of the glass structure with SiO2 addition was proposed according to the structural analysis performed using Raman and X‐ray photoelectron spectroscopies. The evolution stages were as follows: (i) the stage of heavy metal transition from covalent to ionic heavy metals (7.5 wt% < SiO2 < 15 wt%), (ii) the stage of increase in bridging oxygen (15 wt% < SiO2 < 20 wt%), and (iii) the stage of domination of the Si–O network (20 wt% < SiO2 < 25 wt%). The evolution of the glass structure resulted in varying glass chemical durability. Finally, the glass‐forming region of (20–48)PbO–(35–70)Bi2O3–(7.5–25)SiO2 (wt%) and the temperature needed to melt those glasses were determined through the melting test, where radionuclides and toxic heavy metals showed undetectable volatilization during vitrification. Hence, turning LBE waste into glass waste form will be a potential approach for treating Pb–Bi alloy nuclear waste.

show abstract

Leaching behaviors and mechanisms of vitrified forms for the low-level radioactive solid wastes

Kim

et al. 2020

Journal of Hazardous Materials

View full text Add to dashboard Cite

Vitrification of Combustible Dry Active Waste Generated from Korean Nuclear Power Plants

Cited by 4 publications

References 1 publication

Future Plans About the High-Level Radioactive Waste Disposal

Future Plans About the High-Level Radioactive Waste Disposal

Vitrification of lead–bismuth alloy nuclear waste into a glass waste form

Leaching behaviors and mechanisms of vitrified forms for the low-level radioactive solid wastes

Contact Info

Product

Resources

About