392 results found
Bhattacharya G, Zhang S, Smith ME, et al., 2006, Mineralizing magnesium aluminate spinel formation with B2O3, Unified International Technical Conference on Refractories, Publisher: BLACKWELL PUBLISHING, Pages: 3034-3042, ISSN: 0002-7820
McLoughlin SD, Hand RJ, Hyatt NC, et al., 2006, The long term corrosion of glasses: analytical results after 32 years of burial at Ballidon, GLASS TECHNOLOGY-EUROPEAN JOURNAL OF GLASS SCIENCE AND TECHNOLOGY PART A, Vol: 47, Pages: 59-67, ISSN: 0017-1050
Souza GP, Messer PF, Lee WE, 2006, Effect of varying quartz particle size and firing atmosphere on densification of brazilian clay-based stoneware, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 89, Pages: 1993-2002, ISSN: 0002-7820
Ojovan MI, Lee WE, Barinov AS, et al., 2006, Corrosion of low level vitrified radioactive waste in a loamy soil, GLASS TECHNOLOGY-EUROPEAN JOURNAL OF GLASS SCIENCE AND TECHNOLOGY PART A, Vol: 47, Pages: 48-55, ISSN: 0017-1050
Stennett MC, Hyatt NC, Lee WE, et al., 2006, Processing and characterisation of fluorite-related ceramic wasteforms for immobilisation of actinides, Ceramic Transactions, Vol: 176, Pages: 81-90, ISSN: 1042-1122
A number of possible options have been proposed for the encapsulation and immobilisation of long lived actinide (Act) fractions in nuclear waste. Current research on the fabrication of dense, durable crystalline matrices for the safe disposal of fissile plutonium is presented here. In this work three candidate ceramic matrices were investigated: a defect fluorite-structured cubic zirconia, (Zr0.85Y0.15O1.93)0.9(CeO 2)0.1; a pyrochlore, Gd2Zr 1.60Ce0.20Hf0.20O7; and a zirconolite, (Ca0.90Gd0.10)(Zr0.50Ce 0.20Hf0.20Gd0.10)Ti2O7. Homogeneous blends of the ceramic matrix formers and neutron absorbers (gadolinium and hafnium) were produced using a wet milling stage. A dry stage was employed to mix the CeO2 plutonium surrogate with the ceramic matrix formers, analogous to that anticipated for the fabrication of real wasteforms using PuO2. The aim of this study was to compile a matrix of data to enable comparison of the relative merits and drawbacks of various processing routes for each candidate wasteform. An experimental matrix was constructed to investigate the density, phase morphology and microstructure as a function of sintering temperature, time, and consolidation technique, for each target composition. Phase assemblage was examined using X-ray Diffraction (XRD) and Energy Dispersive Spectroscopy (EDS) and the phase morphology by Scanning Electron Microscopy (SEM).
Lee WE, Grimes RW, 2006, Nuclear waste: A UK perspective, Energy Materials: Materials Science and Engineering for Energy Systems, Vol: 1, Pages: 22-24, ISSN: 1748-9237
© 2006 Institute of Materials, Minerals and Mining and W. S. Maney & Son Ltd. Research on immobilisation and storage of nuclear waste is high on the UK’s agenda, driven by decommissioning of redundant reactors and nuclear research facilities and the need to minimise waste in future reactors. There are well understood encapsulation systems for most of our high and intermediate level wastes, but Pu and other ‘difficult’ isotopes, high volume graphite waste, and spent fuels still provide challenges. A holistic approach taking into account development of durable waste forms and both near and far field interaction phenomena will need to be adopted in future research.
Woodward DI, Wise PL, Lee WE, et al., 2006, Space group symmetry of (CaxSr1-x)TiO3 determined using electron diffraction, JOURNAL OF PHYSICS-CONDENSED MATTER, Vol: 18, Pages: 2401-2408, ISSN: 0953-8984
Lee WE, Ojovan MI, Stennett MC, et al., 2006, Immobilisation of radioactive waste in glasses, glass composite materials and ceramics, ADVANCES IN APPLIED CERAMICS, Vol: 105, Pages: 3-12, ISSN: 1743-6753
Lee WE, 2006, The contribution of ceramics to environmental clean up, ADVANCES IN APPLIED CERAMICS, Vol: 105, Pages: 1-1, ISSN: 1743-6753
Ojovan MI, Lee WE, Hand RJ, 2006, Role of ion exchange in the corrosion of nuclear waste glasses, SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXIX, Vol: 932, Pages: 393-+, ISSN: 0272-9172
Stennett MC, Hyatt NC, Maddrell ER, et al., 2006, Microchemical and crystallographic characterisation of fluorite-based ceramic wasteforms, 29th International Symposium on the Scientific Basis for Nuclear Waste Management, Publisher: MATERIALS RESEARCH SOC, Pages: 623-+, ISSN: 0272-9172
Kinoshita H, Uno M, Yamanaka S, et al., 2006, Molten ceramic solidification during molten state processing of HLW, SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXIX, Vol: 932, Pages: 655-+, ISSN: 0272-9172
McLoughlin SD, Hyatt NC, Hand RJ, et al., 2006, Corrosion of archaeological model glasses after 32 years of burial at Ballidon, SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXIX, Vol: 932, Pages: 1065-+, ISSN: 0272-9172
Hyatt NC, Stennett MC, Fiddy SG, et al., 2006, Synthesis and characterisation of transition metal substituted barium hollandite ceramics, 29th International Symposium on the Scientific Basis for Nuclear Waste Management, Publisher: MATERIALS RESEARCH SOC, Pages: 583-+, ISSN: 0272-9172
Zhang S, Jayaseelan DD, Bhattacharya G, et al., 2006, Molten salt synthesis of magnesium aluminate (MgAl2O4) spinel powder, J. Am. Ceram. Soc., Vol: 89, Pages: 1724-1726
Ojovan MI, Lee WE, Hand RJ, 2005, Role of ion exchange in performance of nuclear waste immobilising glasses, Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05, Vol: 2005, Pages: 357-364
The role of diffusion-controlled ion exchange in corrosion of nuclear waste borosilicate glasses has been examined. Ion exchange is the principal radipnuclide release mechanism in conditions when glass network hydrolysis is suppressed, such as in silica-saturated solutions when it persists over geologic time scales. In dilute aqueous solutions ion exchange controls the initial cation release and can dominate for tens and many hundreds of years if temperatures are low. Ion exchange rates are shown to have square root time dependences, Arrhenius-controlled temperature and exponential pH dependences. Numerical estimates of radionuclide release inventory are given for typical nuclear waste radionuclides. Copyright © 2005 by ASME.
Pankov AS, Ojovan MI, Lee WE, et al., 2005, ION-exchange and diffusion parameters of simulant British (Magnox, 75/25 Blended waste) and Russian (K-26) glasses at 40-60°C, Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05, Vol: 2005, Pages: 637-643
Simulant compositions of two British (Magnox and 75/25 Blended) nuclear waste glasses and of Russian K-26 radioactive glass were synthesized and studied to eventually evaluate the role of intrinsic gamma-irradiation on radionuclide release rates. The diffusion coefficient and activation energies of the main glass constituents' release were obtained from a series of leaching experiments over the temperature interval 40° to 60°C at neutral pH and low concentrations of dissolved species. Under these conditions ion-exchange is the main corrosion mechanism of each glass. Normalized release rates of Na, Li, Ca, B and Si were determined after 3, 15 and 27 days test duration. The cation leaching rates for K-26 glass are about an order of magnitude higher than those for both Magnox (MW) and 75/25 glasses. The normalized release rates of cations from K-26 glass at 40° after 27 days are in the range of (3.2-5.7)·10-1 g·m-2d-1 whilst for MW and 75/25 glasses these values are (1.8-3.4)·10-2 and (5.1-6.2)·10-2 g·m-2d-1, respectively. At 60°C the leaching rates increase up to (4.8-7.6) ·10-1 for K-26 glass and (5.0-8.2)·10-2 for MW glass. In most glasses sodium has a normalized release rate higher than those of the network-forming elements. SEM observation reveals an inhomogeneous microstructure in all glasses examined. MW and 75/25 glasses are characterized by segregation of two glassy phases. K-26 glass contains crystalline inclusions although only in small amounts. Surface changes originating from interaction with water have been studied using SEM techniques. K-26 and MW glasses e.g. show formation of altered (secondary) surface layers. Copyright © 2005 by ASME.
Juoi JM, Ojovan MI, Lee WE, 2005, Development of glass-composite materials for radioactive waste immobilisation, Proceedings - 10th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM'05, Vol: 2005, Pages: 341-348
This paper presents an overview of glass composite materials (GCM) development in radioactive waste immobilisation. The different types of GCM and different production methods are discussed including the composition of glass used as well as the immobilised radioactive waste. Preliminary results are also presented on development of low pressure, low temperature sintered glass composites for immobilising spent clinoptilolite arising from water treatment facilities and radionuclide partitioning. Copyright © 2005 by ASME.
Zhang S, Jayaseelan DD, Lee WE, 2005, Molten salt synthesis of high melting complex oxides, UNITECR, 9th Biennial Congress on Refractories
Ojovan MI, Lee WE, 2005, An Introduction to Nuclear Waste Immobilisation, Publisher: Elsevier, ISBN: 9780080455716
The book thoroughly covers all issues surrounding nuclear waste: from where to locate nuclear waste in the environment, through nuclear waste generation and sources, treatment schemes and technologies, immobilisation technologies and waste ...
McConville CJ, Lee WE, 2005, Microstructural development on firing illite and smectite clays compared with that in kaolinite, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 88, Pages: 2267-2276, ISSN: 0002-7820
Bajwa S, Rainforth WM, Lee WE, 2005, Sliding wear behaviour of SiC-Al2O3 nanocomposites, 15th International Conference on Wear of Materials, Publisher: ELSEVIER SCIENCE SA, Pages: 553-561, ISSN: 0043-1648
Ecclestone LJ, Reaney IM, Lee WE, 2005, Correlation of microstructures with electrical performance of Ag-based metal electrode-PZT electroceramic interfaces, JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, Vol: 25, Pages: 1647-1655, ISSN: 0955-2219
Coleman NJ, Lee WE, Slipper IJ, 2005, Interactions of aqueous Cu2+, Zn2+ and Pb2+ ions with crushed concrete fines, JOURNAL OF HAZARDOUS MATERIALS, Vol: 121, Pages: 203-213, ISSN: 0304-3894
Tarvornpanich T, Souza GP, Lee WE, 2005, Microstructural evolution on firing soda-lime-silica glass fluxed whitewares, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 88, Pages: 1302-1308, ISSN: 0002-7820
Zhang S, Lee WE, Zhu B, et al., 2005, Improving hydration resistance of Al powder for carbon containing castables using inorganic-organic hybrid coatings, ADVANCES IN APPLIED CERAMICS, Vol: 104, Pages: 79-82, ISSN: 1743-6753
Ojovan MI, Hand RJ, Ojovan NV, et al., 2005, Corrosion of alkali-boro silicate waste glass K-26 in non-saturated conditions, JOURNAL OF NUCLEAR MATERIALS, Vol: 340, Pages: 12-24, ISSN: 0022-3115
Hand RJ, Short RJ, Morgan S, et al., 2005, Molybdenum in glasses containing vitrified nuclear waste, 7th European-Society-of-Glass Conference on Glass Science and Technology, Publisher: SOC GLASS TECHNOLOGY, Pages: 121-124, ISSN: 0017-1050
Zhang SW, Hashimoto S, Lee WE, 2005, Hydration of aluminum powder in magnesia-containing water, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 88, Pages: 1057-1059, ISSN: 0002-7820
Ojovan MI, Lee WE, 2005, Fragility of oxide melts as a thermodynamic parameter, PHYSICS AND CHEMISTRY OF GLASSES, Vol: 46, Pages: 7-11, ISSN: 0031-9090
This data is extracted from the Web of Science and reproduced under a licence from Thomson Reuters. You may not copy or re-distribute this data in whole or in part without the written consent of the Science business of Thomson Reuters.