Optimized cement blend for the immobilization of simulated borate radioactive liquid waste

IF 1.5 3区 化学 Q3 CHEMISTRY, ANALYTICAL
Gabriel Iklaga, Mojtaba Rostamiparsa, István Tolnai, Nándor Kaposy, Katalin Gméling, Emese Csipa, Csaba Tóbi, Viktória Gável, Péter Kónya, Csaba Szabó, Margit Fábián, Zsuzsanna Szabó-Krausz, Péter Völgyesi
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Abstract

Nuclear power plants use boric acid with different 10B enrichment levels (from natural ratio to 90% 10B) as neutron absorber and at the end this constitutes a high-volume liquid waste. In this study, we aimed to find the optimal ratio of Portland cement and sulfoaluminate cement blend to improve the mechanical and chemical durability of final waste forms for borate immobilization. The standardized ASTM C1308-21 leaching test experimental method in combination with several analytical methods i.e. mechanical test, SEM, XRD, PGAA, ICP-OES, and ICP-MS were used to measure the boron elemental and isotopic leachability and its microstructural effect on the cement hydration characteristics of progressively increasing blend ratios of sulfoaluminate cement in Portland cement. The results indicated that the blend ratio of 20% sulfoaluminate cement to 80% Portland cement showed the best physical stability and lowest boron isotopic leachability from the final waste form.

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来源期刊
CiteScore
2.80
自引率
18.80%
发文量
504
审稿时长
2.2 months
期刊介绍: An international periodical publishing original papers, letters, review papers and short communications on nuclear chemistry. The subjects covered include: Nuclear chemistry, Radiochemistry, Radiation chemistry, Radiobiological chemistry, Environmental radiochemistry, Production and control of radioisotopes and labelled compounds, Nuclear power plant chemistry, Nuclear fuel chemistry, Radioanalytical chemistry, Radiation detection and measurement, Nuclear instrumentation and automation, etc.
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