Study on fused/cast AZS refractories for deployment in vitrification of radioactive waste effluents

作者: Pranesh Sengupta , R.K. Mishra , N. Soudamini , D. Sen , S. Mazumder

DOI: 10.1016/J.JNUCMAT.2015.09.019

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摘要: Abstract ‘Fused/cast Al2O3–ZrO2–SiO2 (FC-AZS)’ is being considered as ‘glass contact refractory’ within ceramic melters, to be used for nuclear waste immobilization. Microstructural analyses reveal random distributions of baddeleyite (ZrO2) aluminosilicate (Al2SiO5) matrix. 27Al and 29Si NMR data suggest that matrix Al occurs in both 4- 6-fold co-ordinations whereas Si prefers a 4-fold environment. Polydispersity pores has been studied with small-angle neutron scattering (SANS) technique. Corrosion rates FC-AZS 6 M HNO3, simulated wastes (500 h exposure), borosilicate melt (975 °C, 800 h exposure) are found 0.38 × 103 μmy−1, 0.13 × 103 μmy−1 4.75 × 103 μmy−1 respectively. A comparison chemical interaction clearly suggests exhibits better durability than AZC refractory (Al2O3–ZrO2–Cr2O3, also similar purpose). Thermal cycling studies indicate retains structural integrity (including compressive strength density) even up 20 cycles.

参考文章(40)
Elisa Gambuzzi, Alfonso Pedone, Maria Cristina Menziani, Frédéric Angeli, Daniel Caurant, Thibault Charpentier, Probing silicon and aluminium chemical environments in silicate and aluminosilicate glasses by solid state NMR spectroscopy and accurate first-principles calculations Geochimica et Cosmochimica Acta. ,vol. 125, pp. 170- 185 ,(2014) , 10.1016/J.GCA.2013.10.025
Mithun Nath, Sandipan Sen, K. Banerjee, A. Ghosh, H.S. Tripathi, Densification behavior and properties of alumina–chrome ceramics: Effect of TiO2 Ceramics International. ,vol. 39, pp. 227- 232 ,(2013) , 10.1016/J.CERAMINT.2012.06.013
A El Hadrami, M Mesnaoui, M Maazaz, J.-J Videau, Kinetic dissolution of phosphate glasses containing toxic heavy metals Journal of Non-crystalline Solids. ,vol. 331, pp. 228- 239 ,(2003) , 10.1016/J.JNONCRYSOL.2003.08.066
Pranesh Sengupta, Interaction study between nuclear waste-glass melt and ceramic melter bellow liner materials Journal of Nuclear Materials. ,vol. 411, pp. 181- 184 ,(2011) , 10.1016/J.JNUCMAT.2011.01.122
A. D. Chervonnyi, N. A. Chervonnaya, Use of Synthetic Calcium Aluminosilicate for Immobilization of Radioactive Wastes Radiochemistry. ,vol. 46, pp. 190- 197 ,(2004) , 10.1023/B:RACH.0000024950.03863.C2
D. Read, C. T. Williams, Degradation of phosphatic waste forms incorporating long-lived radioactive isotopes Mineralogical Magazine. ,vol. 65, pp. 589- 601 ,(2001) , 10.1180/002646101317018415
V. Kain, P. Sengupta, P. K. De, S. Banerjee, Case reviews on the effect of microstructure on the corrosion behavior of austenitic alloys for processing and storage of nuclear waste Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science. ,vol. 36, pp. 1075- 1084 ,(2005) , 10.1007/S11661-005-0201-5
W. E. Lee, M. I. Ojovan, M. C. Stennett, N. C. Hyatt, Immobilisation of radioactive waste in glasses, glass composite materials and ceramics Advances in Applied Ceramics. ,vol. 105, pp. 3- 12 ,(2006) , 10.1179/174367606X81669
Raman K Mishra, Kumaran V Sudarsan, Pranesh Sengupta, Rajesh K Vatsa, Avesh K Tyagi, Chetan P Kaushik, Dasarathi Das, Kanwar Raj, None, Role of Sulfate in Structural Modifications of Sodium Barium Borosilicate Glasses Developed for Nuclear Waste Immobilization Journal of the American Ceramic Society. ,vol. 91, pp. 3903- 3907 ,(2008) , 10.1111/J.1551-2916.2008.02773.X