{"title":"放射性金属氧化物渣基固化体浸出稳定性的最佳铁渣","authors":"Ki Joon Kang , Sia Hwang , Hee Reyoung Kim","doi":"10.1016/j.net.2025.103851","DOIUrl":null,"url":null,"abstract":"<div><div>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<sub>2</sub>O<sub>3</sub>, Cr<sub>2</sub>O<sub>3</sub>, NiO, and Co, was solidified using various additives—including ferro frit 3110, ferro frit 3195, and B<sub>2</sub>O<sub>3</sub>—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<sub>2</sub>O<sub>3</sub>-rich frits substantially improved Cr leaching resistance by strengthening the glass network structure and suppressing ionic mobility. This improvement is attributed to B<sub>2</sub>O<sub>3</sub>'s role in reducing non-bridging oxygen content and increasing network polymerization. As the Cr<sub>2</sub>O<sub>3</sub> 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<sub>2</sub>O<sub>3</sub>.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103851"},"PeriodicalIF":2.6000,"publicationDate":"2025-08-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Optimal ferro frit for leaching stability of radioactive metal oxide sludges-based solidified body\",\"authors\":\"Ki Joon Kang , Sia Hwang , Hee Reyoung Kim\",\"doi\":\"10.1016/j.net.2025.103851\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>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<sub>2</sub>O<sub>3</sub>, Cr<sub>2</sub>O<sub>3</sub>, NiO, and Co, was solidified using various additives—including ferro frit 3110, ferro frit 3195, and B<sub>2</sub>O<sub>3</sub>—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<sub>2</sub>O<sub>3</sub>-rich frits substantially improved Cr leaching resistance by strengthening the glass network structure and suppressing ionic mobility. This improvement is attributed to B<sub>2</sub>O<sub>3</sub>'s role in reducing non-bridging oxygen content and increasing network polymerization. As the Cr<sub>2</sub>O<sub>3</sub> 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<sub>2</sub>O<sub>3</sub>.</div></div>\",\"PeriodicalId\":19272,\"journal\":{\"name\":\"Nuclear Engineering and Technology\",\"volume\":\"57 12\",\"pages\":\"Article 103851\"},\"PeriodicalIF\":2.6000,\"publicationDate\":\"2025-08-11\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Technology\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S173857332500419X\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S173857332500419X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
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 Fe2O3, Cr2O3, NiO, and Co, was solidified using various additives—including ferro frit 3110, ferro frit 3195, and B2O3—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 B2O3-rich frits substantially improved Cr leaching resistance by strengthening the glass network structure and suppressing ionic mobility. This improvement is attributed to B2O3's role in reducing non-bridging oxygen content and increasing network polymerization. As the Cr2O3 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 B2O3.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development