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- 저자 : Vladimir I. Pet’kov (검색결과 2 건)
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Vladimir I. Pet’kov,Alexander S. Shipilov,Anton S. Dmitrienko,Artemy A. Alekseev 한국공업화학회 2018 Journal of Industrial and Engineering Chemistry Vol.57 No.-
MZr2(TO4)x(PO4)3–x (M = Li, Na, K, Rb, Cs; T = As, V) solid solutions, NaFeZr(PO4)2SO4 and Pb2/3FeZr(PO4)7/3(SO4)2/3 with mineral kosnarite structure and KPbMgTi(PO4)3, K5/3MgE4/3(PO4)3 (E = Ti, Zr) with mineral langbeinite structure have been synthesized. According to the yielded results, which encompass thermal expansion data and crystallographic information about the structure of individual compounds and solid solutions, the meaningful selection of compounds with kosnarite and langbeinite structure for novel materials with controllable thermal expansion was carried out. The potassium-, rubidium-, and cesium-containing arsenates, arsenate–phosphates, vanadate–phosphates and Pb2/3FeZr(PO4)7/3(SO4)2/3 are low expansion materials (αav < 2 × 10−6 K−1); sodium–zirconium arsenate and sodium–zirconium and lithium–zirconium arsenate–phosphates, vanadate–phosphates and K5/3MgZr4/3(PO4)3 have intermediate thermal expansion (3 × 10−6 K−1 < αav < 7 × 10−6 K−1); and lithium–zirconium arsenate, KPbMgTi(PO4)3, K5/3MgTi4/3(PO4)3 are the high expansion material (αav > 7 × 10−6 K−1). The present results demonstrate that change of the size of alkali metal cation, anion substitution and varying of solid solution composition can produce kosnarite ceramics with controlled linear thermal expansion coefficients and extremely low thermal expansion anisotropy or langbeinite ceramics with isotropic expansion.
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Vitreous and crystalline phosphate high level waste matrices: Present status and future challenges
Ashish Bohre,Kalpana Avasthi,Vladimir I. Pet’kov 한국공업화학회 2017 Journal of Industrial and Engineering Chemistry Vol.50 No.-
Vitrification is currently the most effective process for immobilization of nuclear waste. However,ubiquitous borosilicate glass is not suitable for immobilization of nuclear waste from advanced reactorssuch as Fast Breeder Reactors (FBR) because solubility of many compounds/elements existing in the spentfuel in borosilicate glasses is quite poor. In order to possess a viable immobilization strategy for wastesarising from advanced reactors, alternatives to borosilicate glasses such as phosphate glasses, glassceramicsand crystalline waste forms are being investigated. This review aims to provide an overview ofnuclear waste immobilization employing phosphate-based glasses, glass-ceramics and crystallineceramic hosts, focusing on structure and properties that make these new matrices suitable for thechallenging task of waste immobilization.
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