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• catalog abstract "In response to growing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the NEA organised the Third Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering. The proceedings of this meeting provide an overview of high-temperature research currently under way, including studies on the behaviour of irradiated graphite and improvements in material properties under high-temperature irradiation. These proceedings also contain recommendations for further international work in the areas of high-temperature engineering.".
• catalog contributor b13301200.
• catalog contributor b13301201.
• catalog created "c2004.".
• catalog date "2004".
• catalog date "c2004.".
• catalog dateCopyrighted "c2004.".
• catalog description "-High-Temperature Reactor Materials: Progress of HTR-M Projects by D. Buckthorpe, M. Davies, R. Couturier, J. van der Laan, J. Hegeman, A. Vreeling, B. Riou, H. Rantala, P. Ennis, G. Haag, K. Kuhn, A. Buenaventura, and B-C. Friedrich -- Neutron Irradiation Effect on the Dimensional Change of Graphite Materials by T. Maruyama -- The Prediction of Irradiation Creep by G. B. Neighbour -- Ion Irradiation Effects on Tensile Properties of Carbon Fibres by A. Kurumada, Y. Imamura, t. Okyu, M. Ishihara, s. Baba, J. Aihara -- Analysis of Crack Propagation in Nuclear Graphite using Three-Point Bending of Sandwiched Specimens by L. Shi, S. L. Fok, B. J. Marsden, L. Ng, P. Mummery, and J. Marrow -- Study on Multi-Axial Strength Model Taking Account of Grain/Pore Microstructure by S. Hanawa, M. Ishihara, Y. Motohashi -- Examining the Issues of Scale in Nuclear Graphite Components by M.J. Holt, G. B. Neighbour -- ".
• catalog description "Fabrication of Tailored Ceramics by Colloidal Processing and their Application by Y. Sakka, T. S. Suzuki, T. Uchikoshi, K. Hiraga, T. Shibata, M. Ishihara -- Session V. Development of In-Core Material Characterisation and Instrumentation Method -- -Towards In Situ Monitoring and Characterisation of Material Surfaces under Irradiation at Elevated Temperatures by M. Yamawaki, K. Yamaguchi, G-N Luo, T. Terai, and M. Ishihara -- In-Reactor Optical Dosimetry in High-Temperature Engineering Test Reactor by T. Shikama, K. Toh, M. Ishihara, M. Narui, S. Nagata, S. Baba, B. Tsuchiya, N. Shamoto, and T. Kakuta -- Study on High-Temperature Radioluminescent Ceramics for HTTR application by K. Toh, S. Nagata, B. Tsuchiya, T. Suzuki, T. Shikama, M. Ishihara, M. Fujisuka, T. Tanabe, and S. Yamamoto -- List of Participants".
• catalog description "Foreword -- Executive Summary -- Session I. Overviews of High-Temperature Research in Each Country and Organisation -- -IAEA High-Temperature Gas-Cooled Reactor Activities by M. Methnani -- Research Activities of te Nuclear Graphite Research Group at the University of Manchester, UK by B. J> Marsden, A.S. L. Fok, J. Marrow, and P. Mummery -- Codes and Standards Development fro Graphite-Moderated Nuclear Reactors by T. Burchell, M. Srinivasan, and D. Naus -- CEA R&D Programme on Structural Materials for Future Gas-Cooled Nuclear Systems by P. Billot, J. L. Seran, M. T. Carrillat, H. Burlet, A. Terlain, and J. P. Bonal -- Current Status of the Innovative Basic Research on High-Temperature Engineering using the HTTR by M. Ishihara, T. Shibata, S. Ishino, T. Terai, T. Ohoshima, T. Okyu, Y. Motohashi, M. Yamaha, T. Shikama, C. Mori, and S. Shiozawa -- Session II. Basic Studies on Behaviour of Irradiated Graphite-Carbon Including their Composites -- ".
• catalog description "In response to growing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the NEA organised the Third Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering. The proceedings of this meeting provide an overview of high-temperature research currently under way, including studies on the behaviour of irradiated graphite and improvements in material properties under high-temperature irradiation. These proceedings also contain recommendations for further international work in the areas of high-temperature engineering.".
• catalog description "Includes bibliographical references.".
• catalog description "Session III. Other Topics in the Field of High-Temperature Engineering with Emphasis on Basic Studies -- -Design of Spherical Fuel element for a Gas-Cooled Fast Reactor by W.F.G. van Rooijen, J. L. Kloosterman, H. van Dam and T.H.J.J. van der Hagen -- Modelling of Fission Product Diffusion in Hihg-Temperature Gas Reactor Fuel by P. Guillemier -- Session IV. Improvement in Material Properties through High-Temperature Irradiation -- -Introduction of Phosphorus Atoms in Silicon Carbide using Nuclear Transmuation Doping at Elevated Temperatures by T. Ohshima, N. Morishita, T. Kamiya, J. Isoya, S. Baba, J. Aihara, M. Yamaji, M. Ishihara -- Modification of HTSC by High-Temperature Neutron Irradiation by T. Terai, Y. Nagamoto, N. Chikumoto, and M. Ishihara -- Effectsof Supersplastic Deformation on Thermo Physical Properties of Tetragonal Zirconia Polycrystals by Y. Motohashi, C. Wan, T. Sakuma, S. Harjo, T. Shibata, M. Ishihara, S. Baba, and T. Toshiya -- ".
• catalog extent "277 p. :".
• catalog identifier "9264016015".
• catalog isPartOf "Nuclear Science, 1990-0643.".
• catalog isPartOf "Nuclear science".
• catalog issued "2004".
• catalog issued "c2004.".
• catalog language "eng".
• catalog publisher "Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development,".
• catalog subject "Gas cooled reactors Congresses.".
• catalog subject "Heat resistant materials Congresses.".
• catalog subject "High temperatures Congresses.".
• catalog subject "TK9203.G3 B372 2004".
• catalog tableOfContents "-High-Temperature Reactor Materials: Progress of HTR-M Projects by D. Buckthorpe, M. Davies, R. Couturier, J. van der Laan, J. Hegeman, A. Vreeling, B. Riou, H. Rantala, P. Ennis, G. Haag, K. Kuhn, A. Buenaventura, and B-C. Friedrich -- Neutron Irradiation Effect on the Dimensional Change of Graphite Materials by T. Maruyama -- The Prediction of Irradiation Creep by G. B. Neighbour -- Ion Irradiation Effects on Tensile Properties of Carbon Fibres by A. Kurumada, Y. Imamura, t. Okyu, M. Ishihara, s. Baba, J. Aihara -- Analysis of Crack Propagation in Nuclear Graphite using Three-Point Bending of Sandwiched Specimens by L. Shi, S. L. Fok, B. J. Marsden, L. Ng, P. Mummery, and J. Marrow -- Study on Multi-Axial Strength Model Taking Account of Grain/Pore Microstructure by S. Hanawa, M. Ishihara, Y. Motohashi -- Examining the Issues of Scale in Nuclear Graphite Components by M.J. Holt, G. B. Neighbour -- ".
• catalog tableOfContents "Fabrication of Tailored Ceramics by Colloidal Processing and their Application by Y. Sakka, T. S. Suzuki, T. Uchikoshi, K. Hiraga, T. Shibata, M. Ishihara -- Session V. Development of In-Core Material Characterisation and Instrumentation Method -- -Towards In Situ Monitoring and Characterisation of Material Surfaces under Irradiation at Elevated Temperatures by M. Yamawaki, K. Yamaguchi, G-N Luo, T. Terai, and M. Ishihara -- In-Reactor Optical Dosimetry in High-Temperature Engineering Test Reactor by T. Shikama, K. Toh, M. Ishihara, M. Narui, S. Nagata, S. Baba, B. Tsuchiya, N. Shamoto, and T. Kakuta -- Study on High-Temperature Radioluminescent Ceramics for HTTR application by K. Toh, S. Nagata, B. Tsuchiya, T. Suzuki, T. Shikama, M. Ishihara, M. Fujisuka, T. Tanabe, and S. Yamamoto -- List of Participants".
• catalog tableOfContents "Foreword -- Executive Summary -- Session I. Overviews of High-Temperature Research in Each Country and Organisation -- -IAEA High-Temperature Gas-Cooled Reactor Activities by M. Methnani -- Research Activities of te Nuclear Graphite Research Group at the University of Manchester, UK by B. J> Marsden, A.S. L. Fok, J. Marrow, and P. Mummery -- Codes and Standards Development fro Graphite-Moderated Nuclear Reactors by T. Burchell, M. Srinivasan, and D. Naus -- CEA R&D Programme on Structural Materials for Future Gas-Cooled Nuclear Systems by P. Billot, J. L. Seran, M. T. Carrillat, H. Burlet, A. Terlain, and J. P. Bonal -- Current Status of the Innovative Basic Research on High-Temperature Engineering using the HTTR by M. Ishihara, T. Shibata, S. Ishino, T. Terai, T. Ohoshima, T. Okyu, Y. Motohashi, M. Yamaha, T. Shikama, C. Mori, and S. Shiozawa -- Session II. Basic Studies on Behaviour of Irradiated Graphite-Carbon Including their Composites -- ".
• catalog tableOfContents "Session III. Other Topics in the Field of High-Temperature Engineering with Emphasis on Basic Studies -- -Design of Spherical Fuel element for a Gas-Cooled Fast Reactor by W.F.G. van Rooijen, J. L. Kloosterman, H. van Dam and T.H.J.J. van der Hagen -- Modelling of Fission Product Diffusion in Hihg-Temperature Gas Reactor Fuel by P. Guillemier -- Session IV. Improvement in Material Properties through High-Temperature Irradiation -- -Introduction of Phosphorus Atoms in Silicon Carbide using Nuclear Transmuation Doping at Elevated Temperatures by T. Ohshima, N. Morishita, T. Kamiya, J. Isoya, S. Baba, J. Aihara, M. Yamaji, M. Ishihara -- Modification of HTSC by High-Temperature Neutron Irradiation by T. Terai, Y. Nagamoto, N. Chikumoto, and M. Ishihara -- Effectsof Supersplastic Deformation on Thermo Physical Properties of Tetragonal Zirconia Polycrystals by Y. Motohashi, C. Wan, T. Sakuma, S. Harjo, T. Shibata, M. Ishihara, S. Baba, and T. Toshiya -- ".
• catalog title "Basic studies in the field of high-temperature engineering : third information exchange meeting, Ibaraki-ken, Japan, 11-12 September 2003 / co-organized by the Japan Atomic Energy Research Institute.".
• catalog type "text".