Research on chemical durability of iron phosphate glass wasteforms vitrifying SrF2 and CeF3
| Autor: | Yanbo Qiao, Liu Xueyang, Ma Hongjun, Zhenghua Qian |
|---|---|
| Rok vydání: | 2018 |
| Předmět: |
Nuclear and High Energy Physics
Materials science Molten salt reactor Borosilicate glass Oxide Radioactive waste Thorium chemistry.chemical_element 02 engineering and technology 021001 nanoscience & nanotechnology 010403 inorganic & nuclear chemistry 01 natural sciences Durability 0104 chemical sciences law.invention chemistry.chemical_compound Nuclear Energy and Engineering chemistry law General Materials Science Iron phosphate 0210 nano-technology Fluoride Nuclear chemistry |
| Zdroj: | Journal of Nuclear Materials. 508:286-291 |
| ISSN: | 0022-3115 |
| DOI: | 10.1016/j.jnucmat.2018.05.043 |
| Popis: | A part of the radioactive waste produced in the Thorium Molten Salt Reactor (TMSR) will be present as fluorides. Because of some characters of fluoride, it is undesirable for immobilizing the waste as other usual oxide waste in borosilicate glass that often produces immiscibility. However, iron phosphate glasses have been made with up to 30 wt% SrF2 and 20 wt% CeF3, and about 20 wt% SrF2 and CeF3 combined. The iron phosphate glass matrix mixed with fluoride waste could be melted at temperatures between 1050 °C and 1200 °C in only 30–60 min, its melting temperature is lower than that of borosilicate glass. Powder X-ray diffraction (XRD) showed that the glassy wasteforms that contains more than 20% wt% SrF2 and CeF3 mixture, or more than 20 wt% CeF3 would start crystallizing. The product consistency test (PCT) was used to identify the chemical durability of the glass. Glass powder (−100 to +200 mesh) after washing was soaked in 10 ml of deionized water at 90 °C for 7 days. The normalized elemental mass release of elements Sr, Ce and F were calculated at the level of 10−3 g/m2, through the concentration of element measured after PCT, that was equivalent to or better than that of borosilicate glass wasteforms. Iron phosphate glasses are concluded to be a practical alternative for vitrifying the radioactive waste of TMSR. |
| Databáze: | OpenAIRE |
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