393 results found
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.
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
Ojovan MI, Lee WE, 2011, GLASSY AND GLASS COMPOSITE NUCLEAR WASTEFORMS, ADVANCES IN MATERIALS SCIENCE FOR ENVIRONMENTAL AND NUCLEAR TECHNOLOGY II, Vol: 227, Pages: 203-216, ISSN: 1042-1122
Desimone D, Dlouhy I, Lee WE, et al., 2010, Optically-transparent oxide fibre-reinforced glass matrix composites, 12th International Conference on the Physics of Non-Crystalline Solids (PNCS12), Publisher: ELSEVIER SCIENCE BV, Pages: 2591-2597, ISSN: 0022-3093
Ojovan MI, Lee WBE, 2010, Connectivity and glass transition in disordered oxide systems, 12th International Conference on the Physics of Non-Crystalline Solids (PNCS12), Publisher: ELSEVIER SCIENCE BV, Pages: 2534-2540, ISSN: 0022-3093
Jayaseelan DD, Jackson H, Eakins E, et al., 2010, Laser modified microstructures in ZrB2, ZrB2/SiC and ZrC, Workshop on Aerospace Materials for Extreme Environments, Publisher: ELSEVIER SCI LTD, Pages: 2279-2288, ISSN: 0955-2219
Desimone D, Jayaseelan DD, Pang B, et al., 2010, Oxide Fibre Reinforced Gglass Matrix Compositeswith ZrO2 Interfaces, European Journal of Glass Science and Technology Part A, Vol: 50 (2), Pages: 121-126, ISSN: 1753-3546
Lee WE, Sa R, 2010, Challenges and Oopportunities for the Refractories Industry - An Academic Perspective, IREFCON10, Pages: 7-17
Ojovan MI, Juoi JM, Boccaccini AR, et al., 2010, Glass Composite Materials for Nuclear and Hazardous Waste Immobilisation, Mater. Res. Soc. Symp. Proc., Vol: 1107
Lee WE, 2010, Future Challenges and opportunities in Refractories, Minerals and Materials Review, Pages: 38-39
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.