Works matching DE "RADIOACTIVE waste vitrification"
Results: 51
Preliminary results of corrosion monitoring studies of carbon steel overpack exposed to supercontainer concrete buffer.
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- Corrosion Engineering, Science & Technology, 2014, v. 49, n. 6, p. 485, doi. 10.1179/1743278214Y.0000000216
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Long term integrity of overpack closure weld for HLW geological disposal Part 1 - prediction and evaluation method for structural integrity of weld joint.
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- Corrosion Engineering, Science & Technology, 2011, v. 46, n. 2, p. 165, doi. 10.1179/1743278210Y.0000000016
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STRUCTURAL CHARACTERIZATION OF SOME NEW GLASS CERAMICS FROM INDUSTRIAL WASTES.
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- Annals of DAAAM & Proceedings, 2009, p. 1539
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Comparison of ultrastructure and morphology of mouse ovarian follicles after conventional and direct cover vitrification using different concentrations of ethylene glycol.
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- Iranian Journal of Reproductive Medicine, 2009, v. 7, n. 2, p. 45
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Crystallization kinetics of borosilicate glasses for CHROMPIC nuclear waste vitrification.
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- Physics & Chemistry of Glasses: European Journal of Glass Science & Technology Part B, 2015, v. 56, n. 2, p. 49, doi. 10.13036/17533562.56.2.049
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Using Vitrification for Sewage Sludge Combustion Ash Disposal.
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- Polish Journal of Environmental Studies, 2015, v. 24, n. 5, p. 1889, doi. 10.15244/pjoes/36080
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Microstructure Characterization of Simulated Tri-Isotropic Particles Embedded in Alkaline Borosilicate Glass.
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- International Journal of Applied Glass Science, 2011, v. 2, n. 4, p. 334, doi. 10.1111/j.2041-1294.2011.00064.x
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Retention of Sulfate in Savannah River Site High-Level Radioactive Waste Glass.
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- International Journal of Applied Glass Science, 2010, v. 1, n. 4, p. 388, doi. 10.1111/j.2041-1294.2010.00035.x
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Glass Transition Behavior: A Generic Phenomenological Approach.
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- International Journal of Applied Glass Science, 2010, v. 1, n. 3, p. 221, doi. 10.1111/j.2041-1294.2010.00020.x
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Nuclear Waste Vitrification in the United States: Recent Developments and Future Options.
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- International Journal of Applied Glass Science, 2010, v. 1, n. 3, p. 309, doi. 10.1111/j.2041-1294.2010.00023.x
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Expression of Heat Shock Protein (HSP AlA) and MnSOD Genes Following Vitrification of Mouse Mll Oocytes with Cryotop Method.
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- Yakhteh Medical Journal, 2010, v. 12, n. 1, p. 113
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Preparation and characterisation of glass product with modified composition for vitrification of high level radioactive waste.
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- Journal of Thermal Analysis & Calorimetry, 2013, v. 112, n. 1, p. 103, doi. 10.1007/s10973-012-2811-7
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Kinetic method by using calorimetry to mechanism of epoxy-amine cure reaction.
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- Journal of Thermal Analysis & Calorimetry, 2003, v. 74, n. 1, p. 29, doi. 10.1023/A:1026313416464
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NON-COMBUSTIBLE WASTE VITRIFICATION WITH PLASMA TORCH MELTER.
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- Journal of Environmental Science & Health. Part A. Toxic/Hazardous Substances & Environmental Engineering, 2001, v. 36, n. 5, p. 861, doi. 10.1081/ESE-100103766
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Corrosion Resistance of Refractories in Melts of Glasses Used to Immobilize Radioactive Wastes.
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- Refractories & Industrial Ceramics, 2016, v. 57, n. 2, p. 160, doi. 10.1007/s11148-016-9947-0
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Refractory materials for the melters of plants used in vitrification of radioactive wastes.
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- Refractories & Industrial Ceramics, 2010, v. 51, n. 3, p. 183, doi. 10.1007/s11148-010-9285-6
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Tratamiento de residuos industriales mediante tecnología de plasma.
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- DYNA - Ingeniería e Industria, 2011, v. 86, n. 1, p. 80, doi. 10.6036/3851
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- Article
Vitrification of low silica fly ash: suitability of resulting glass ceramics for architectural or electrical insulator applications.
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- Advances in Applied Ceramics: Structural, Functional & Bioceramics, 2009, v. 108, n. 1, p. 27, doi. 10.1179/174367509X344980
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Use of vitrified bottom ashes of municipal solid waste incinerators in bituminous mixtures in substitution of natural sands.
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- Advances in Applied Ceramics: Structural, Functional & Bioceramics, 2009, v. 108, n. 1, p. 33, doi. 10.1179/174367608X364285
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Leaching behaviour of a glassy slag and derived glass ceramics from arc plasma vitrification of hospital wastes.
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- Advances in Applied Ceramics: Structural, Functional & Bioceramics, 2009, v. 108, n. 1, p. 67, doi. 10.1179/174367608X366337
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Vitrification of toxic wastes: a brief review.
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- Advances in Applied Ceramics: Structural, Functional & Bioceramics, 2006, v. 105, n. 1, p. 21, doi. 10.1179/174367606X81687
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Behavior of technetium in nuclear waste vitrification processes.
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- Journal of Radioanalytical & Nuclear Chemistry, 2015, v. 305, n. 1, p. 287, doi. 10.1007/s10967-014-3900-9
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The Hanford cleanup: What's taking so long?
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- Bulletin of the Atomic Scientists, 2014, v. 70, n. 4, p. 37, doi. 10.1177/0096340214539115
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Vitrification of a high-level iron-aluminate wastes simulator in a cold crucible.
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- Atomic Energy, 2010, v. 108, n. 1, p. 33, doi. 10.1007/s10512-010-9253-8
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Glassy Wasteforms for Nuclear Waste Immobilization.
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- Metallurgical & Materials Transactions. Part A, 2011, v. 42, n. 4, p. 837, doi. 10.1007/s11661-010-0525-7
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New melter pours first vitrified waste.
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- Nuclear Future, 2018, v. 14, n. 2, p. 8
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Novel glass formulations for post-operational clean out of highly active storage tanks.
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- Nuclear Future, 2017, v. 13, n. 4, p. 54
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ILW and the future.
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- Nuclear Future, 2014, v. 10, n. 4, p. 64
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Vitrification to be evaluated at Sellafield.
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- Nuclear Future, 2014, v. 10, n. 1, p. 7
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Vitrification of Legacy and Intermediate Level Radioactive Wastes: Opportunities and Challenges.
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- Nuclear Future, 2010, v. 6, n. 5, p. 250
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Vitrified waste returns set to begin.
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- Nuclear Future, 2009, v. 5, n. 6, p. 292
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GeoMelt® Waste Vitrification.
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- Nuclear Future, 2009, v. 5, n. 5, p. 276
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Plasma Vitrification Technology for the treatment of Nuclear Waste.
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- Nuclear Future, 2009, v. 5, n. 5, p. 267
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The Impact of Increased Waste Loading on Vitrified HLW Quality & Durability.
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- Nuclear Future, 2009, v. 5, n. 4, p. 211
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ABB - AMEC - BNFL Alliance keeps project on time and on budget.
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- Nuclear Future, 2005, v. 1, n. 1, p. 41
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- Article
Cs containing borosilicate waste glasses.
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- Optica Applicata, 2008, v. 38, n. 1, p. 237
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Simulation of cooling and solidification of three-dimensional bulk borosilicate glass: effect of structural relaxations.
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- Mechanics of Time-Dependent Materials, 2014, v. 18, n. 1, p. 81, doi. 10.1007/s11043-013-9215-3
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Using Polymerization, Glass Structure, and Quasicrystalline Theory to Produce High Level Radioactive Borosilicate Glass Remotely: A 20+ Year Legacy.
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- Journal of the South Carolina Academy of Science, 2017, v. 15, n. 1, p. 12
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Radioactive Wastes.
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- Water Environment Research (10614303), 2016, v. 88, n. 10, p. 1486, doi. 10.2175/106143016X14696400495299
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Zn-K EXAFS investigations on ZnS/ZnO containing vitrified ashes from municipal incinerator facilities.
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- Journal of Materials Science, 2001, v. 36, n. 20, p. 5017, doi. 10.1023/A:1011802202743
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Evaluation of effect of reducing additives during vitrification via simulation and experiment.
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- Journal of the Air & Waste Management Association (Taylor & Francis Ltd), 2013, v. 63, n. 10, p. 1182, doi. 10.1080/10962247.2013.809389
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The effect on long term aqueous durability of variations in the composition of UK vitrified HLW product.
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- Glass Technology: European Journal of Glass Science & Technology Part A, 2012, v. 53, n. 5, p. 211
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Heterogeneous multi-agent optimization framework with application to synthesizing optimal nuclear waste blends.
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- Clean Technologies & Environmental Policy, 2018, v. 20, n. 1, p. 137, doi. 10.1007/s10098-017-1464-4
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Alteration of basalt glasses: implications for modelling the long-term stability of nuclear waste glasses.
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- Nature, 1985, p. 252, doi. 10.1038/314252a0
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Subliquidus Phase Relations in the Low-Alumina Section of the Na<sub>2</sub>O-Al<sub>2</sub>O<sub>3</sub>-P<sub>2</sub>O<sub>5</sub> System and the Radioactive Waste Vitrification.
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- Glass Physics & Chemistry, 2018, v. 44, n. 6, p. 591, doi. 10.1134/S1087659618060135
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Characteristics of vitrified liquid radioactive wastes prepared with the use of aqueous silica sols.
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- Glass Physics & Chemistry, 2009, v. 35, n. 4, p. 397, doi. 10.1134/S1087659609040087
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Closing the Fuel Cycle Through Vitrification - The West Valley Demonstration Project.
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- Journal of the Institute of Nuclear Materials Management, 2013, v. 41, n. 4, p. 6
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Effects of Quartz Particle Size and Sucrose Addition on Melting Behavior of a Melter Feed for High-Level Waste Glass.
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- Journal of the Institute of Nuclear Materials Management, 2010, v. 39, n. 1, p. 31
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Liquid-Liquid Phase Separation Process in Borosilicate Liquids Enriched in Molybdenum and Phosphorus Oxides.
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- Journal of the American Ceramic Society, 2011, v. 94, n. 2, p. 447, doi. 10.1111/j.1551-2916.2010.04131.x
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Composition-Structure Relationships in Simplified Nuclear Waste Glasses: 1. Mixed Alkali Borosilicate Glasses.
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- Journal of the American Ceramic Society, 2011, v. 94, n. 1, p. 92, doi. 10.1111/j.1551-2916.2010.04066.x
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