Optimized cement blend for the immobilization of simulated borate radioactive liquid waste
Abstract Nuclear power plants use boric acid with different 10 B enrichment levels (from natural ratio to 90% 10 B) 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.
Authors
- Mojtaba Rostamiparsa
- Zsuzsanna Szabó-Krausz (ORCID: https://orcid.org/0000-0002-4454-8700)
- Csaba Szabó (ORCID: https://orcid.org/0000-0002-1580-6344)
- Péter Völgyesi (ORCID: https://orcid.org/0000-0002-7478-4317)
- Emese Csipa
- István Tolnai (ORCID: https://orcid.org/0000-0003-3853-7981)
- Viktória Gável
- Katalin Gméling (ORCID: https://orcid.org/0000-0003-0253-0745)
- Péter Kónya (ORCID: https://orcid.org/0009-0009-8061-6510)
- Margit Fábián (ORCID: https://orcid.org/0000-0002-6528-4695)
- Csaba Tóbi (ORCID: https://orcid.org/0000-0003-4865-3775)
- Gabriel Iklaga (ORCID: https://orcid.org/0009-0008-1998-9652)
- Nándor Kaposy (ORCID: https://orcid.org/0009-0005-0675-4318)
Institutions
- Eötvös Loránd University (HU)
- Mining and Geological Survey of Hungary (HU)
- Research and Development for Silicates and Ceramics (HU)
- Geological Institute (RU)
- HUN-REN Centre for Energy Research (HU)
Publication Details
- Journal
- Journal of Radioanalytical and Nuclear Chemistry
- Published
- 2025-02-01
- DOI
- https://doi.org/10.1007/s10967-024-09957-x
- Citations
- 6
- Primary Topic
- Graphite, nuclear technology, radiation studies
- Type
- article
- Field-Weighted Citation Impact
- 3.11
Funders
- Magyar Tudományos Akadémia
- Eötvös Loránd Tudományegyetem
- Tempus Közalapítvány