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• catalog abstract "In response to increasing 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 a Second Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering. These proceedings provide an overview of the activities being carried out in eight countries, the improvement of material properties for HTGR application, in-core monitoring methods and properties of irradiated graphite, and HTGR fuel fabrication and performance.".
• catalog contributor b12559590.
• catalog contributor b12559591.
• catalog created "c2002.".
• catalog date "2002".
• catalog date "c2002.".
• catalog dateCopyrighted "c2002.".
• catalog description "An Analysis of Irradiation Creep in Nuclear Graphites by G. B. Neighbour and P.J. Hacker -- Planning for Disposal of Irradiated Graphite: Issues for the New Generation of HTRs by B. MeEnaney, A. J. Wickham, and M. Dubourg -- Status of IAEA International Database on Irradiateed Graphite Properties with Respect to HTR Engineering Issues by P. J. Hacker, B. McEnaney, A. J. Wickham and G. Haag -- Session V. Basic Studies on HTGR Fuel Fabrication and Performance -- Evidence of Dramatic Fission Product Release from Irradiated Nuclear Ceramics by L. Thome, A. Gentils, F. Garrido, and J. Jagielski -- Method of Reactor Tests ot HTGR Fuel Elements at an Impulse Loading by A. Chernikov, V. Eremeev, and V. Ivanov -- Gas Reactor TRISO-Coasted Particle Fuel Modelling Activities at the Idaho National Engineering and Environmental Laboratory by D. Petti, G. Miller, J. Maki, D. Varacalle, and J. Buongiorno -- Session Summaries -- Recommendations -- List of Participants".
• catalog description "Current Status of High-Temperature Engineering and Research in France by D. Hittner, F. Carre, and J. Roualt -- Overview of High-Temperature Reactor Engineering and Research by K. Kugeler, P-W. Phlippen, M. Kugeler, and H. Hohn -- The Contribution of UK Organisations in the Development of New High Temperature Reactors by A. J. Wickham, I. M. Coe, P. J. Bramah, T. J. Abram -- Session II. Improvement in Material Properties by High-Temperature Irradiation -- Improvement in Ductility of Refractory Metals by Neutron Irradiation by H. Kurishita -- Effects of Superplastic Deformation on Thermal and Mechanical Properties of 3Y-TZP Cermamics (Review) by M. Ishihara, T. Shibata, S. Baba, T. Hoshiya, C. Wan, and Y. Motohashi -- Development of an Innovative Carbon-Based Ceramic Material: Application in High-Temperature, Neutron, and Hydrogen Environment by C. H. Wu -- A Carbon Dioxide Partial Condensation Cycle for High-Temperature Reactors by T. Nitawaki, and Y. Kato -- ".
• catalog description "Development of High-Temperature Irradiation Techniques Utilising the Japan Materials Testing Reactor by M. Narui, T. Shikama, M. Yamasaki, and H. Matsui -- Session IV. Basic Studies on Behaviour of Irradiated Graphite/Carbon and Ceramic Materials Including their Composites under both Operation and Storage Conditions -- Investigation of High-Temperature Reactor Materials by D. Buckthorpe, r. Couturier, B. van der Schaaf, B. riou, H.Rantala, R. Moormann, F. Alonso, B-C. Friedrich -- Radially Keyed Graphite Moderator Cores: An Investigation into the Stability of Finite Element Models by W.R. Taylor, M. D. Warner, G. B. Neighbour,B. McEnaney, S. E. Clift -- Understanding of Mechanical Properties of Graphite on the Basis of Mesoscopic Microstructure (Review) by M. Ishihara, t. Shibata, T. Takahashi, S. Baba, and T. Hoshiya -- Advanced Graphite Oxidation Models by R. Moormann, H-K. Hinssen -- Irradiation-Creep in Graphite - A Review by B. J. Marsden and S. D. Preston -- ".
• catalog description "Foreword -- Executive Summary -- Opening Session -- -Welcome Address by C. Kessler -- Opening Address by S. Ishino -- Session I. Overviews of High Temperature Engineering Research in Each Country and Organisation -- Research Activities on High-Temperature Gas-Cooled Reactors (HTRs) in the 5th EURATOM RTD Framework Programme by J. Martin-Bermejo, M. Hugon, and G. Van Goethem -- Update on IAEA High-Temperature Gas-Cooled Reactor Activities by J. Kendall and M. Methnani -- Present Status of the Innovative Basic Research on High-Temperature Engineering using the HTTR by Y. Sudo, T. Hoshiya, M. Ishihara, T.Shibata, S. Ishino, T. Terai, T. Oku, Y. MOtohashi, S. Tagawa, Y. Katsumura, M. Yamawaki, T. Shikama, C. Mori, H. Itoh, and S. Shiozawa -- Present Status in the Netherlands of Research Relevant to High Temperature Gas-Cooled Reactor Design by J. C. Kuijper, A. I. van Heek, J. B. M.de Haas, R. Conrad, M. Burghartz, and J.L. Kloosterman -- ".
• catalog description "In response to increasing 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 a Second Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering. These proceedings provide an overview of the activities being carried out in eight countries, the improvement of material properties for HTGR application, in-core monitoring methods and properties of irradiated graphite, and HTGR fuel fabrication and performance.".
• catalog description "Includes bibliographical references.".
• catalog description "Session III. Development of In-Core Material Characterisation Methods and Irradiation Facility -- Development of the I-I Type Irradiation Equipment for HTTR by T. Shibata, T. Kikuchi, S. Miyamoto, K. Ogura and Y. Ishigaki -- Application of Optical Diagnostics in High-Temperature Gas-Cooled Systems by T. Shikama, M. Narui, T. Katuta, M.Ishitsuka, K. Hayashi, T. Sagawa, and T. Hoshiya -- Measurement Method of In-Core Neutron and Gamma Ray Distributions with Scintillator Optical Fibre Detector and Self-Powered Detector by C. MOri, a. Uritani, T. Kakuta, M. Katagiri, T. Shikama, M. Nakazawa, T. Iguchi, J. Kawarabayashi, I. Kimura, H. Kobayashi, and S. Hayashi -- Development of In-Core Test Capabilities for Material Characterisation by C. Vitanza -- Application of Work Function Measuring Technique to Monitoring/Characterisation of Material Surfaces under Irradiation by G-N Luo, t.Terai, M. Yamawaki, K. Yamaguchi -- ".
• catalog extent "356 p. :".
• catalog identifier "9264197966".
• catalog isPartOf "Nuclear Science, 1990-0643.".
• catalog isPartOf "Nuclear science".
• catalog issued "2002".
• catalog issued "c2002.".
• 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 tableOfContents "An Analysis of Irradiation Creep in Nuclear Graphites by G. B. Neighbour and P.J. Hacker -- Planning for Disposal of Irradiated Graphite: Issues for the New Generation of HTRs by B. MeEnaney, A. J. Wickham, and M. Dubourg -- Status of IAEA International Database on Irradiateed Graphite Properties with Respect to HTR Engineering Issues by P. J. Hacker, B. McEnaney, A. J. Wickham and G. Haag -- Session V. Basic Studies on HTGR Fuel Fabrication and Performance -- Evidence of Dramatic Fission Product Release from Irradiated Nuclear Ceramics by L. Thome, A. Gentils, F. Garrido, and J. Jagielski -- Method of Reactor Tests ot HTGR Fuel Elements at an Impulse Loading by A. Chernikov, V. Eremeev, and V. Ivanov -- Gas Reactor TRISO-Coasted Particle Fuel Modelling Activities at the Idaho National Engineering and Environmental Laboratory by D. Petti, G. Miller, J. Maki, D. Varacalle, and J. Buongiorno -- Session Summaries -- Recommendations -- List of Participants".
• catalog tableOfContents "Current Status of High-Temperature Engineering and Research in France by D. Hittner, F. Carre, and J. Roualt -- Overview of High-Temperature Reactor Engineering and Research by K. Kugeler, P-W. Phlippen, M. Kugeler, and H. Hohn -- The Contribution of UK Organisations in the Development of New High Temperature Reactors by A. J. Wickham, I. M. Coe, P. J. Bramah, T. J. Abram -- Session II. Improvement in Material Properties by High-Temperature Irradiation -- Improvement in Ductility of Refractory Metals by Neutron Irradiation by H. Kurishita -- Effects of Superplastic Deformation on Thermal and Mechanical Properties of 3Y-TZP Cermamics (Review) by M. Ishihara, T. Shibata, S. Baba, T. Hoshiya, C. Wan, and Y. Motohashi -- Development of an Innovative Carbon-Based Ceramic Material: Application in High-Temperature, Neutron, and Hydrogen Environment by C. H. Wu -- A Carbon Dioxide Partial Condensation Cycle for High-Temperature Reactors by T. Nitawaki, and Y. Kato -- ".
• catalog tableOfContents "Development of High-Temperature Irradiation Techniques Utilising the Japan Materials Testing Reactor by M. Narui, T. Shikama, M. Yamasaki, and H. Matsui -- Session IV. Basic Studies on Behaviour of Irradiated Graphite/Carbon and Ceramic Materials Including their Composites under both Operation and Storage Conditions -- Investigation of High-Temperature Reactor Materials by D. Buckthorpe, r. Couturier, B. van der Schaaf, B. riou, H.Rantala, R. Moormann, F. Alonso, B-C. Friedrich -- Radially Keyed Graphite Moderator Cores: An Investigation into the Stability of Finite Element Models by W.R. Taylor, M. D. Warner, G. B. Neighbour,B. McEnaney, S. E. Clift -- Understanding of Mechanical Properties of Graphite on the Basis of Mesoscopic Microstructure (Review) by M. Ishihara, t. Shibata, T. Takahashi, S. Baba, and T. Hoshiya -- Advanced Graphite Oxidation Models by R. Moormann, H-K. Hinssen -- Irradiation-Creep in Graphite - A Review by B. J. Marsden and S. D. Preston -- ".
• catalog tableOfContents "Foreword -- Executive Summary -- Opening Session -- -Welcome Address by C. Kessler -- Opening Address by S. Ishino -- Session I. Overviews of High Temperature Engineering Research in Each Country and Organisation -- Research Activities on High-Temperature Gas-Cooled Reactors (HTRs) in the 5th EURATOM RTD Framework Programme by J. Martin-Bermejo, M. Hugon, and G. Van Goethem -- Update on IAEA High-Temperature Gas-Cooled Reactor Activities by J. Kendall and M. Methnani -- Present Status of the Innovative Basic Research on High-Temperature Engineering using the HTTR by Y. Sudo, T. Hoshiya, M. Ishihara, T.Shibata, S. Ishino, T. Terai, T. Oku, Y. MOtohashi, S. Tagawa, Y. Katsumura, M. Yamawaki, T. Shikama, C. Mori, H. Itoh, and S. Shiozawa -- Present Status in the Netherlands of Research Relevant to High Temperature Gas-Cooled Reactor Design by J. C. Kuijper, A. I. van Heek, J. B. M.de Haas, R. Conrad, M. Burghartz, and J.L. Kloosterman -- ".
• catalog tableOfContents "Session III. Development of In-Core Material Characterisation Methods and Irradiation Facility -- Development of the I-I Type Irradiation Equipment for HTTR by T. Shibata, T. Kikuchi, S. Miyamoto, K. Ogura and Y. Ishigaki -- Application of Optical Diagnostics in High-Temperature Gas-Cooled Systems by T. Shikama, M. Narui, T. Katuta, M.Ishitsuka, K. Hayashi, T. Sagawa, and T. Hoshiya -- Measurement Method of In-Core Neutron and Gamma Ray Distributions with Scintillator Optical Fibre Detector and Self-Powered Detector by C. MOri, a. Uritani, T. Kakuta, M. Katagiri, T. Shikama, M. Nakazawa, T. Iguchi, J. Kawarabayashi, I. Kimura, H. Kobayashi, and S. Hayashi -- Development of In-Core Test Capabilities for Material Characterisation by C. Vitanza -- Application of Work Function Measuring Technique to Monitoring/Characterisation of Material Surfaces under Irradiation by G-N Luo, t.Terai, M. Yamawaki, K. Yamaguchi -- ".
• catalog title "Basic studies in the field of high-temperature engineering ; second information exchange meeting, Paris, France, 10-12 October 2001.".
• catalog type "text".