Research Regarding Vitirfication of Radioactive Cs in High-level Liquid Waste
This paper discussed processing radioactive Cs isotopes in Spent fuel reprocessing High-level liquid waste(HLLW),which have high potential radiotoxcity,using glass,ceramic or glass-ceramic vitrification.Firstly,the generation and character of radioactive Cs is introduced.The decay,heat generation theory and their influence during processing radioactive Cs are analyzed.Then the research about glass and ceramic consolidation of Cs around the world is discussed,including silicate and phosphate glass formulation also single and multi phase ceramic material.Specially the research regards Cs vitrification via hollandite is introduced.With developing of the two-steps cold-crucible vitrification technology,using ceramic and glass-ceramic phase to vitrificate radioactive Cs isotopes in Power reactor spent fuel reprocessing HLLW is becoming more suitable,which also facing challenges.
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