02134nas a2200265   4500008004100000022001400041245010400055210006900159260007300228300001200301490000800313520113300321653006501454653003301519653002501552100002201577700002201599700001801621700001201639700001701651700002401668700003201692700001701724856012701741       2015                        eng d  a0022-311500aStudy on fused/cast AZS refractories for deployment in vitrification of radioactive waste effluents0 aStudy on fusedcast AZS refractories for deployment in vitrificat  aPO BOX 211, 1000 AE AMSTERDAM, NETHERLANDSbELSEVIER SCIENCE BVcDEC  a144-1540 v4673 a<p>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) within aluminosilicate (Al2SiO5) matrix. Al-27 and Si-29 NMR data suggest that within aluminosilicate matrix Al occurs in both 4- and 6-fold co-ordinations whereas Si prefers a 4-fold environment. Polydispersity of pores has been studied with small-angle neutron scattering (SANS) technique. Corrosion rates of FC-AZS within 6 M HNO3, simulated wastes (500 h exposure), and borosilicate melt (975 degrees C, 800 h exposure) are found to be 0.38 x 10(3) mu my(-1), 0.13 x 10(3) mu my(-1) and 4.75 x 10(3) mu my(-1) respectively. A comparison of chemical interaction data clearly suggests that FC-AZS exhibits better chemical durability than AZC refractory (Al2O3-ZrO2-Cr2O3, also used for similar purpose). Thermal cycling studies indicate that FC-AZS retains structural integrity (including compressive strength and density) even up to 20 cycles. (C) 2015 Elsevier B.V. All rights reserved.</p>10aInteraction between refractory material and hazardous liquid10aNuclear waste immobilization10aVitrification melter1 aSengupta, Pranesh1 aMishra, Raman, K.1 aSoudamini, N.1 aSen, D.1 aMazumder, S.1 aKaushik, Chetan, P.1 aAjithkumar, Thalasseril, G.1 aBanerjee, K.  uhttps://library.ncl.res.in/content/study-fusedcast-azs-refractories-deployment-vitrification-radioactive-waste-effluents-001870nas a2200205   4500008004100000245013500041210006900176260000800245300000900253490001000262520113500272100002501407700002101432700001701453700001901470700001201489700001701501700001901518856012701537       2017                        eng d00aStructure and short time degradation studies of sodium zirconium phosphate ceramics loaded with simulated fast breeder (FBR) waste0 aStructure and short time degradation studies of sodium zirconium  cAPR  a5-120 v487  3 aSodium zirconium phosphate (NZP) ceramics have been prepared using conventional sintering and hot isostatic pressing (HIP) routes. The structure of NZP ceramics, prepared using the HIP route, has been compared with conventionally sintered NZP using a combination of X-ray diffraction (XRD) and (P-31 and Na-23) nuclear magnetic resonance (NMR) spectroscopy techniques. It is observed that NZP with no waste loading is aggressive toward the steel HIP -can during hot isostatic compaction and significant fraction of cations from the steel enter the ceramic material. Waste loaded NZP samples (10 wt% simulated FBR waste) show significantly low can -interaction and primary NZP phase is evident in this material. Upon exposure of can -interacted and waste loaded NZP to boiling water and steam, P-31 NMR does not detect any major modifications in the network structure. However, the Na-23 NMR spectra indicate migration of Na+ ions from the surface and possible re -crystallization. This is corroborated by Small -Angle Neutron Scattering (SANS) data and Scanning Electron Microscopy (SEM) measurements carried out on these samples.1 aAnanthanarayanan, A.1 aAmbashta, R., D.1 aSudarsan, V.1 aAjithkumar, T.1 aSen, D.1 aMazumder, S.1 aWattal, P., K.  uhttps://library.ncl.res.in/content/structure-and-short-time-degradation-studies-sodium-zirconium-phosphate-ceramics-loaded