401 results found
Lee WE, Gilbert M, Murphy ST, et al., 2013, Opportunities for Advanced Ceramics and Composites in the Nuclear Sector, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 96, Pages: 2005-2030, ISSN: 0002-7820
Zapata-Solvasa E, Jayaseelan DD, Brown PM, et al., 2013, Thermal properties of La2O3-doped ZrB2- and HfB2-based ultra-high temperature ceramics
Thermal properties of La2O3-doped ZrB2- and HfB2-based ultra high temperature ceramics (UHTCs) have been measured at temperatures from room temperature to 2000 °C and compared with SiC-doped ZrB2- and HfB2-based UHTCs and monolithic ZrB2 and HfB2. Thermal conductivities of La2O3-doped UHTCs remain constant around 55–60 W/mK from 1500 °C to 1900 °C while SiC-doped UHTCs showed a trend to decreasing values over this range.
Cui B, Zapata-Solvas E, Reece MJ, et al., 2013, Microstructure and High-temperature Oxidation Behavior of Ti3AlC2/W Composites, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 96, Pages: 584-591, ISSN: 0002-7820
Lee WE, Ojovan MI, Jantzen CM, 2013, Radioactive waste management and contaminated site clean-up: Processes, technologies and international experience, Radioactive Waste Management and Contaminated Site Clean-Up: Processes, Technologies and International Experience, Pages: 1-879
Radioactive waste management and contaminated site clean-up reviews radioactive waste management processes, technologies, and international experiences. Part one explores the fundamentals of radioactive waste including sources, characterisation, and processing strategies. International safety standards, risk assessment of radioactive wastes and remediation of contaminated sites and irradiated nuclear fuel management are also reviewed. Part two highlights the current international situation across Africa, Asia, Europe, and North America. The experience in Japan, with a specific chapter on Fukushima, is also covered. Finally, part three explores the clean-up of sites contaminated by weapons programmes including the USA and former USSR. © 2013 Woodhead Publishing Limited. All rights reserved.
Lee WE, Ojovan MI, 2013, Fundamentals of radioactive waste (RAW): Science, sources, classification and management strategies, Pages: 3-49
Classification systems for the types of radioactive waste (RAW) are described along with sources of controlled wastes (including from power production, military programmes, medical uses and research reactors) and uncontrolled or accidental releases. Options for managing controlled wastes from pretreatment, treatment, conditioning and storage stages through to transportation to final disposal are considered. Immobilisation (wasteform), temporary storage and permanent disposal options including near surface, deep and very deep geological disposal are covered as well as strategies for uncontrolled releases. © 2013 Woodhead Publishing Limited All rights reserved.
Ojovan MI, Lee WE, 2013, An Introduction to Nuclear Waste Immobilisation: Second Edition, An Introduction to Nuclear Waste Immobilisation: Second Edition, Pages: 1-362
Drawing on the authors' extensive experience in the processing and disposal of waste, An Introduction to Nuclear Waste Immobilisation, Second Edition examines the gamut of nuclear waste issues from the natural level of radionuclides in the environment to geological disposal of waste-forms and their long-term behavior. It covers all-important aspects of processing and immobilization, including nuclear decay, regulations, new technologies and methods. Significant focus is given to the analysis of the various matrices used, especially cement and glass, with further discussion of other matrices such as bitumen. The final chapter concentrates on the performance assessment of immobilizing materials and safety of disposal, providing a full range of the resources needed to understand and correctly immobilize nuclear waste. The fully revised second edition focuses on core technologies and has an integrated approach to immobilization and hazards Each chapter focuses on a different matrix used in nuclear waste immobilization: cement, bitumen, glass and new materials Keeps the most important issues surrounding nuclear waste - such as treatment schemes and technologies and disposal - at the forefront. © 2014 Elsevier Ltd All rights reserved.
This chapter describes the Fukushima Daiichi nuclear power plant (NPP) accident starting with the reactors' location and sequence of events which caused the accident. The amount of radioactive materials released and its composition, dispersion of radioactive materials over land and sea, contamination effects on food and the environment and radiation effects on human health are all addressed along with the current clean-up programme and future plans. However, it is expected that it will take 30-40. years to decommission the damaged facilities. © 2013 Woodhead Publishing Limited All rights reserved.
Fan Z, Liu Y, Wang J, et al., 2013, China: Experience of radioactive waste (RAW) management, Pages: 697-722
Progress in the management of China's radioactive waste (RAW) is described, including waste generation, waste management policy, and current practices in regional disposal of low and intermediate level waste (LILW) and development of a geological disposal facility for hight level waste (HlW). © 2013 Woodhead Publishing Limited All rights reserved.
Jantzen CM, Lee WE, Ojovan MI, 2013, Radioactive waste (RAW) conditioning, immobilization, and encapsulation processes and technologies: Overview and advances, Pages: 171-272
The main immobilization technologies that have been demonstrated for radioactive waste disposal are cementation, bituminization, and vitrification. Vitrification is currently the most widely used technology for the treatment of high level radioactive wastes (HLW) throughout the world. Nations that have generated HLW are immobilizing in either alkali borosilicate glass or alkali aluminophosphate glass. The compositions of nuclear waste glasses are tailored for easy preparation and melting, avoidance of glass-in-glass phase separation, avoidance of uncontrolled crystallization, and acceptable chemical durability. Future waste generation is driven by interest in sources of clean energy. The development of advanced waste forms is a necessary component of the new nuclear power plant (NPP) flowsheets. A brief summary is given of existing and advanced waste forms and processing technologies. © 2013 Woodhead Publishing Limited All rights reserved.
Jackson HF, Lee WE, 2012, Properties and characteristics of zrc, Vol: 2, Pages: 339-372
Zirconium carbide (ZrC) possesses a combination of thermodynamic, thermal, and mechanical properties that are promising for nuclear fuel applications requiring high-temperature resistance and structural integrity. This chapter reviews the literature evaluating ZrC properties as affected by temperature, as well as across the wide range of stoichiometry reported for ZrCx (x ≈ 0-0.5). Studies to date of the performance of ZrC under neutron and ion irradiation are summarized. © 2012 Elsevier Ltd All rights reserved.
Cui B, Jayaseelan DD, Lee WE, 2012, TEM study of the early stages of Ti2AlC oxidation at 900 degrees C, SCRIPTA MATERIALIA, Vol: 67, Pages: 830-833, ISSN: 1359-6462
Zhang S, Jayaseelan DD, Li ZS, et al., 2006, Molten salt synthesis of ceramic materials, EUCHEM conference on Molten Salts and Ionic Liquids
Li Z, Zhang S, Lee WE, 2012, Molten Salt Synthesis of LaA1O3 Powder at Low Temperatures, Pages: 219-228
Ye J, Zhang S, Lee WE, 2012, Novel low temperature synthesis and characterisation of hollow silicon carbide spheres, MICROPOROUS AND MESOPOROUS MATERIALS, Vol: 152, Pages: 25-30, ISSN: 1387-1811
Jayaseelan DD, Zapata-Solvas E, Brown P, et al., 2012, In situ Formation of Oxidation Resistant Refractory Coatings on SiC-Reinforced ZrB2 Ultra High Temperature Ceramics, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 95, Pages: 1247-1254, ISSN: 0002-7820
Cui B, Sa R, Jayaseelan DD, et al., 2012, Microstructural evolution during high-temperature oxidation of spark plasma sintered Ti2AlN ceramics, ACTA MATERIALIA, Vol: 60, Pages: 1079-1092, ISSN: 1359-6454
Desimone D, Jayaseelan DD, Lee WE, et al., 2012, Development of ZrO2 interfaces for all-oxide composites, COMPOSITES SCIENCE AND TECHNOLOGY, Vol: 72, Pages: 197-203, ISSN: 0266-3538
Paul A, Jayaseelan DD, Venugopal S, et al., 2012, UHTC composites for hypersonic applications, AMERICAN CERAMIC SOCIETY BULLETIN, Vol: 91, Pages: 22-28, ISSN: 0002-7812
Cui B, Jayaseelan DD, Lee WE, 2011, Reply to comment on "Microstructural evolution during high-temperature oxidation of Ti2AlC ceramics", SCRIPTA MATERIALIA, Vol: 65, Pages: 933-934, ISSN: 1359-6462
Jackson HF, Jayaseelan DD, Manara D, et al., 2011, Laser Melting of Zirconium Carbide: Determination of Phase Transitions in Refractory Ceramic Systems, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 94, Pages: 3561-3569, ISSN: 0002-7820
Gilbert M, Davoisne C, Stennett MC, et al., 2011, Krypton and helium irradiation damage in yttria-stabilised zirconia, Materials Research Society Symposium Proceedings, Vol: 1298, Pages: 197-202, ISSN: 0272-9172
A candidate matrix material for inert matrix fuel (IMF), yttria-stabilised zirconia (YSZ) has been doped with Nd3+ as a surrogate for Pu 3+. To simulate and assess the effects of fission gas accommodation and alpha decay on the microstructure, samples of (Y0.1425,Nd 0.05,Zr0.8075)O1.904 have been irradiated with 2 MeV 36Kr+ ions, at fluences of 1×1014 and 5×1015 cm-2, and 200 keV 4He + ions at fluences of 1×1014, 5×10 15 and 1×1017 cm-2. Analysis by transmission electron microscopy (TEM) of thin sections prepared by focussed ion beam (FIB) milling revealed damage was only observed at the highest 36Kr+ and 4He+ fluences. Monte Carlo simulations using the TRIM code showed that it is only at these fluences that the level of atomic displacements was sufficient to result in observable defect cluster formation within the material. © 2011 Materials Research Society.
Ojovan MI, Lee WE, 2011, Glassy and Glass Composite Nuclear Wasteforms, Advances in Materials Science for Environmental and Nuclear Technology II, Pages: 203-216, ISBN: 9781118060001
© 2011 The American Ceramic Society. The current status of vitrification techniques for immobilisation of nuclear wastes in glasses and glass composite materials (GCM) are reviewed. One-stage and two-stage processes are described along with the compositions and properties of the resulting glassy wasteforms. Techniques for assessing wasteform durability are discussed along with the mechanisms of corrosion on contact with groundwater.
Gilbert M, Davoisne C, Stennett M, et al., 2011, Krypton and helium irradiation damage in neodymium-zirconolite, JOURNAL OF NUCLEAR MATERIALS, Vol: 416, Pages: 221-224, ISSN: 0022-3115
Davoisne C, Stennett MC, Hyatt NC, et al., 2011, Krypton irradiation damage in Nd-doped zirconolite and perovskite, JOURNAL OF NUCLEAR MATERIALS, Vol: 415, Pages: 67-73, ISSN: 0022-3115
Rose PB, Woodward DI, Ojovan MI, et al., 2011, Crystallisation of a simulated borosilicate high-level waste glass produced on a full-scale vitrification line, JOURNAL OF NON-CRYSTALLINE SOLIDS, Vol: 357, Pages: 2989-3001, ISSN: 0022-3093
Cui B, Jayaseelan DD, Lee WE, 2011, Microstructural evolution during high-temperature oxidation of Ti2AlC ceramics, ACTA MATERIALIA, Vol: 59, Pages: 4116-4125, ISSN: 1359-6454
Ojovan MI, Lee WE, 2011, Glassy Wasteforms for Nuclear Waste Immobilization, METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, Vol: 42A, Pages: 837-851, ISSN: 1073-5623
Eakins E, Jayaseelan DD, Lee WE, 2011, Toward Oxidation-Resistant ZrB2-SiC Ultra High Temperature Ceramics, METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, Vol: 42A, Pages: 878-887, ISSN: 1073-5623
Jayaseelan DD, de Sa RG, Brown P, et al., 2011, Reactive infiltration processing (RIP) of ultra high temperature ceramics (UHTC) into porous C/C composite tubes, JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, Vol: 31, Pages: 361-368, ISSN: 0955-2219
Jayaseelan DD, Wang Y, Hilmas GE, et al., 2011, TEM investigation of hot pressed-10 vol.% SiC-ZrB2 composite, ADVANCES IN APPLIED CERAMICS, Vol: 110, Pages: 1-7, ISSN: 1743-6753
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