Optimal ferro frit for leaching stability of radioactive metal oxide sludges-based solidified body

In nuclear power plants, the corrosion of metallic components exposed to radioactive liquid waste and coolant can result in the formation of sludge. This study examined the optimization of ferro frit additives to enhance the leaching stability of solidified radioactive sludge. Specifically, simulated sludge, composed of Fe 2 O 3 , Cr 2 O 3 , NiO, and Co, was solidified using various additives—including ferro frit 3110, ferro frit 3195, and B 2 O 3 —and evaluated for leaching stability under ANSI/ANS 16.1 conditions. Among the four target elements, Fe, Ni, and Co consistently demonstrated excellent leaching resistance, while Cr required further immobilization. Co, a key nuclide in leaching resistance assessments for radioactive waste disposal, exhibited low leachate concentrations under all tested conditions. The addition of B 2 O 3 -rich frits substantially improved Cr leaching resistance by strengthening the glass network structure and suppressing ionic mobility. This improvement is attributed to B 2 O 3 's role in reducing non-bridging oxygen content and increasing network polymerization. As the Cr 2 O 3 and NiO content in the sludge increased, the sintering temperature required for stable solidification rose from 950 to 1050 °C. These findings demonstrate that producing chemically durable solidified radioactive sludge suitable for final disposal requires both thermal and compositional optimization, particularly through the incorporation of B 2 O 3 .

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Publication Details

Journal
Nuclear Engineering and Technology
Published
2025-08-11
DOI
https://doi.org/10.1016/j.net.2025.103851
Citations
1
Primary Topic
Graphite, nuclear technology, radiation studies
Type
article
Field-Weighted Citation Impact
0.52

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article

Optimal ferro frit for leaching stability of radioactive metal oxide sludges-based solidified body

Ki Joon Kang, Hee Reyoung Kim, Sia Hwang
1 citations
Nuclear Engineering and Technology
Graphite, nuclear technology, radiation studies
0.52
article

Optimal ferro frit for leaching stability of radioactive metal oxide sludges-based solidified body

Ki Joon Kang, Hee Reyoung Kim, Sia Hwang
article en
1 citations

Abstract

In nuclear power plants, the corrosion of metallic components exposed to radioactive liquid waste and coolant can result in the formation of sludge. This study examined the optimization of ferro frit additives to enhance the leaching stability of solidified radioactive sludge. Specifically, simulated sludge, composed of Fe 2 O 3 , Cr 2 O 3 , NiO, and Co, was solidified using various additives—including ferro frit 3110, ferro frit 3195, and B 2 O 3 —and evaluated for leaching stability under ANSI/ANS 16.1 conditions. Among the four target elements, Fe, Ni, and Co consistently demonstrated excellent leaching resistance, while Cr required further immobilization. Co, a key nuclide in leaching resistance assessments for radioactive waste disposal, exhibited low leachate concentrations under all tested conditions. The addition of B 2 O 3 -rich frits substantially improved Cr leaching resistance by strengthening the glass network structure and suppressing ionic mobility. This improvement is attributed to B 2 O 3 's role in reducing non-bridging oxygen content and increasing network polymerization. As the Cr 2 O 3 and NiO content in the sludge increased, the sintering temperature required for stable solidification rose from 950 to 1050 °C. These findings demonstrate that producing chemically durable solidified radioactive sludge suitable for final disposal requires both thermal and compositional optimization, particularly through the incorporation of B 2 O 3 .

Nuclear Engineering and TechnologyVol. 57(12)
Korea Atomic Energy Research Institute (KR), Ulsan National Institute of Science and Technology (KR)
Ministry of Trade, Industry and Energy, National Research Foundation of Korea, Ministry of Education, Science and Technology, Korea Institute of Energy Technology Evaluation and Planning
Openalex Percentile: Top 34%
Graphite, nuclear technology, radiation studies
0.52
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