Medium-Temperature Glass-Composite Phosphate Materials for the Immobilization of Chloride Radioactive Waste
Among the many radiochemical problems, the search for new materials and technologies for the immobilization of radioactive waste remains relevant, and the range continues to change and expand. The possibility of immobilizing the spent chloride electrolyte after the pyrochemical processing of the mix...
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| Format: | Article |
| Language: | English |
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MDPI AG
2023-09-01
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| Series: | Journal of Composites Science |
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| Online Access: | https://www.mdpi.com/2504-477X/7/9/363 |
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| author | Anna V. Frolova Ksenia Y. Belova Sergey E. Vinokurov |
| author_facet | Anna V. Frolova Ksenia Y. Belova Sergey E. Vinokurov |
| author_sort | Anna V. Frolova |
| collection | DOAJ |
| description | Among the many radiochemical problems, the search for new materials and technologies for the immobilization of radioactive waste remains relevant, and the range continues to change and expand. The possibility of immobilizing the spent chloride electrolyte after the pyrochemical processing of the mixed uranium-plutonium spent nuclear fuel of the new fast reactor BREST-OD-300 on lead coolant into glass-composite phosphate materials synthesized at temperatures of 650–750 °C was studied. The structure of the obtained samples was studied using XRD and SEM/EDS methods. It has been shown that the spent electrolyte simulator components create stable mixed pyrophosphate phases in the glass composite structure. The materials were found to have high hydrolytic stability. This indicates the promise of using phosphate glass composites as materials for the reliable immobilization of the spent electrolyte. |
| first_indexed | 2024-03-10T22:36:03Z |
| format | Article |
| id | doaj.art-33f85325a55645adaebb5955f1241a07 |
| institution | Directory Open Access Journal |
| issn | 2504-477X |
| language | English |
| last_indexed | 2024-03-10T22:36:03Z |
| publishDate | 2023-09-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Journal of Composites Science |
| spelling | doaj.art-33f85325a55645adaebb5955f1241a072023-11-19T11:22:22ZengMDPI AGJournal of Composites Science2504-477X2023-09-017936310.3390/jcs7090363Medium-Temperature Glass-Composite Phosphate Materials for the Immobilization of Chloride Radioactive WasteAnna V. Frolova0Ksenia Y. Belova1Sergey E. Vinokurov2Vernadsky Institute of Geochemistry and Analytical Chemistry of Russian Academy of Sciences, 19 Kosygin St., 119991 Moscow, RussiaVernadsky Institute of Geochemistry and Analytical Chemistry of Russian Academy of Sciences, 19 Kosygin St., 119991 Moscow, RussiaVernadsky Institute of Geochemistry and Analytical Chemistry of Russian Academy of Sciences, 19 Kosygin St., 119991 Moscow, RussiaAmong the many radiochemical problems, the search for new materials and technologies for the immobilization of radioactive waste remains relevant, and the range continues to change and expand. The possibility of immobilizing the spent chloride electrolyte after the pyrochemical processing of the mixed uranium-plutonium spent nuclear fuel of the new fast reactor BREST-OD-300 on lead coolant into glass-composite phosphate materials synthesized at temperatures of 650–750 °C was studied. The structure of the obtained samples was studied using XRD and SEM/EDS methods. It has been shown that the spent electrolyte simulator components create stable mixed pyrophosphate phases in the glass composite structure. The materials were found to have high hydrolytic stability. This indicates the promise of using phosphate glass composites as materials for the reliable immobilization of the spent electrolyte.https://www.mdpi.com/2504-477X/7/9/363phosphate glass compositeradioactive wastehigh-level wastespent electrolytechloridesimmobilization |
| spellingShingle | Anna V. Frolova Ksenia Y. Belova Sergey E. Vinokurov Medium-Temperature Glass-Composite Phosphate Materials for the Immobilization of Chloride Radioactive Waste Journal of Composites Science phosphate glass composite radioactive waste high-level waste spent electrolyte chlorides immobilization |
| title | Medium-Temperature Glass-Composite Phosphate Materials for the Immobilization of Chloride Radioactive Waste |
| title_full | Medium-Temperature Glass-Composite Phosphate Materials for the Immobilization of Chloride Radioactive Waste |
| title_fullStr | Medium-Temperature Glass-Composite Phosphate Materials for the Immobilization of Chloride Radioactive Waste |
| title_full_unstemmed | Medium-Temperature Glass-Composite Phosphate Materials for the Immobilization of Chloride Radioactive Waste |
| title_short | Medium-Temperature Glass-Composite Phosphate Materials for the Immobilization of Chloride Radioactive Waste |
| title_sort | medium temperature glass composite phosphate materials for the immobilization of chloride radioactive waste |
| topic | phosphate glass composite radioactive waste high-level waste spent electrolyte chlorides immobilization |
| url | https://www.mdpi.com/2504-477X/7/9/363 |
| work_keys_str_mv | AT annavfrolova mediumtemperatureglasscompositephosphatematerialsfortheimmobilizationofchlorideradioactivewaste AT kseniaybelova mediumtemperatureglasscompositephosphatematerialsfortheimmobilizationofchlorideradioactivewaste AT sergeyevinokurov mediumtemperatureglasscompositephosphatematerialsfortheimmobilizationofchlorideradioactivewaste |