Publications
493 results found
Li Z, Lee WE, Zhang S, 2007, Low-temperature synthesis of CaZrO<sub>3</sub> powder from molten salts, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 90, Pages: 364-368, ISSN: 0002-7820
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- Citations: 66
Li Z, Zhang S, Lee WE, 2007, Molten salt synthesis of zinc aluminate powder, JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, Vol: 27, Pages: 3407-3412, ISSN: 0955-2219
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- Citations: 48
Pankov AS, Batyukhnova OG, Ojovan MI, et al., 2007, Simulation of self-irradiation of high-sodium content nuclear waste glasses, SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXX, Vol: 985, Pages: 353-+, ISSN: 0272-9172
Li Z, Zhang S, Lee WE, 2007, Molten salt synthesis of LaAlO<sub>3</sub> powder at low temperatures, JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, Vol: 27, Pages: 3201-3205, ISSN: 0955-2219
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- Citations: 72
Bhattacharya G, Zhang S, Jayaseelan DD, et al., 2007, Mineralizing effect of Li2B4O7 and Na2B4O7 on magnesium aluminate spinel formation, J. Am. Ceram. Soc., Vol: 90, Pages: 97-106
Jayaseelan DD, Zhang S, Hashimoto S, et al., 2007, Template formation of magnesium aluminate (MgAl2O4) spinel microplatelets in molten salt, J. Europ. Ceram. Soc., Vol: 27, Pages: 4745-4749
Harris PG, Lee W, McClelland AW, et al., 2007, Stage position measurement for e-bearn lithography tool, Conference on Emerging Lithographic Technologies XI, Publisher: SPIE-INT SOC OPTICAL ENGINEERING, ISSN: 0277-786X
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- Citations: 1
Ojovan MI, Lee WE, 2006, Topologically disordered systems at the glass transition, JOURNAL OF PHYSICS-CONDENSED MATTER, Vol: 18, Pages: 11507-11520, ISSN: 0953-8984
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- Citations: 55
Ojovan MI, Pankov A, Lee WE, 2006, The ion exchange phase in corrosion of nuclear waste glasses, JOURNAL OF NUCLEAR MATERIALS, Vol: 358, Pages: 57-68, ISSN: 0022-3115
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- Citations: 81
Coleman NJ, Brassington DS, Raza A, et al., 2006, Calcium silicate sorbent from secondary waste ash: Heavy metals-removal from acidic solutions, ENVIRONMENTAL TECHNOLOGY, Vol: 27, Pages: 1089-1099, ISSN: 0959-3330
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- Citations: 12
Bhattacharya G, Zhang S, Smith ME, et al., 2006, Mineralizing magnesium aluminate spinel formation with B<sub>2</sub>O<sub>3</sub>, Unified International Technical Conference on Refractories, Publisher: WILEY, Pages: 3034-3042, ISSN: 0002-7820
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- Citations: 30
Steele I, Clay N, Lee W, et al., 2006, A free market in telescope time II: a test implementation, Publisher: SPIE
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
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- Citations: 10
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
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- Citations: 17
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
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- Citations: 16
Zhang S, Jayaseelan DD, Lee WE, 2006, Molten salt synthesis of high melting complex oxides, UNITECR, 9th Biennial Congress on Refractories
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, 2006, Stuart Derbyshire responds [6], Scientist, Vol: 20, ISSN: 0890-3670
Woodward DI, Wise PL, Lee WE, et al., 2006, Space group symmetry of (Ca<i><sub>x</sub></i>Sr<sub>1-<i>x</i></sub>)TiO<sub>3</sub> determined using electron diffraction, JOURNAL OF PHYSICS-CONDENSED MATTER, Vol: 18, Pages: 2401-2408, ISSN: 0953-8984
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- Citations: 18
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
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.
Lee WE, Wadsworth MEJ, Hotopf M, 2006, The protective role of trait anxiety: a longitudinal cohort study., Psychol Med, Vol: 36, Pages: 345-351, ISSN: 0033-2917
BACKGROUND: Most research has indicated that neuroticism (or trait anxiety) is associated with only negative outcomes. Such a common, heritable and variable trait is expected to have beneficial as well as detrimental effects. We tested the hypothesis that trait anxiety in childhood reduces the risk of dying from accidental causes in early adult life. METHOD: A longitudinal, population-based, birth cohort study of 4,070 men and women born in the UK in 1946. Trait anxiety as judged by teachers when the participants were 13 and 15 years old, and the neuroticism scale of a Maudsley Personality Inventory (MPI) when the participants were 16 years old. Outcomes were deaths, deaths from accidents, non-fatal accidents, and non-fatal accidents requiring medical intervention. RESULTS: Adolescents with low trait anxiety had higher rates of accident mortality to age 25 [low anxiety at 13, hazard ratio (HR) 5.9, low anxiety at 15, HR 1.8]. Low trait anxiety in adolescence was associated with decreased non-accidental mortality after age 25 (low anxiety at 13, HR 0; low anxiety at 15, HR 0.7; low neuroticism at 16, HR 0.7). CONCLUSIONS: High trait anxiety measured in adolescence is associated with reduced accidents and accidental death in early adulthood but higher rates of non-accidental mortality in later life.
Lee WE, 2006, The contribution of ceramics to environmental clean up, ADVANCES IN APPLIED CERAMICS, Vol: 105, Pages: 1-1, ISSN: 1743-6753
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- Citations: 35
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
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- Citations: 289
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
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- Citations: 1
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
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- Citations: 2
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
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- Citations: 3
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
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- Citations: 4
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
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
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- Citations: 1
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.
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