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논문 기본 정보

자료유형
학술저널
저자정보
Rafika Souag (University of Boumerdes) Nour elhayet Kamel (Nuclear Research Centre of Algiers) Dalila Moudir (Nuclear Research Centre of Algiers) Yasmina Mouheb (Nuclear Research Centre of Algiers) Fayrouz Aouchiche (Nuclear Research Centre of Algiers)
저널정보
한양대학교 세라믹공정연구센터 Journal of Ceramic Processing Research Journal of Ceramic Processing Research 제23권 제3호
발행연도
2022.6
수록면
304 - 311 (8page)

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This paper studies the nuclear glass ceramic based on aluminosilicate glass. It is proposed the addition of TiO2 on thecrystalline phase. The structure and chemical durability have been investigated. The materials with four TiO2 contents,ranging from 4.11 to 7.11 wt.%, are synthesized by a discontinuous method. The 7.11 wt.% TiO2 glass ceramic synthesis wasnot successful and crystallizes during the melting stage. For the others materials, Archimedes density ranges between 2.891and 2.962 g/cm3. For the majority of materials, X-ray diffraction analysis allows the identification of an aluminosilicate thatbelongs to pyroxenes silicates family as the initial phase, powelite and calzirtite. These phases are known as radionuclides’sequestration minerals. Both SEM and DTA analyses confirm these findings. The FTIR analysis of materials reveals thecomplex glass-ceramics chemical composition. MCC1 and MCC2 tests, performed on selected glass ceramic materials, indicatethat the materials containing 4.11 and 5.11 wt.% TiO2 are the most durable against Si, Al, Mg and Ce elements release, inMCC2 test; the Ce (minor actinide surrogate) leaching rate being negligible (193.7?10?9 kg/m2d after 28 leaching days for 5.11wt.% of TiO2 content). These results make valuable conclusions for the selection of the glass ceramic suitable to the high-levelwaste disposal.

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