Nuclear Science

Nuclear Energy Agency

1990-0643 (online)
1990-0651 (print)
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A series of publications from the OECD Nuclear Energy Agency on various aspects of nuclear science. The publications in this series (analytical reports and proceedings) provide research results and technical expertise in basic disciplines such as nuclear and radiation physics, thermal hydraulics, neutronics, fuel chemistry and material science which are needed to maintain a high level of performance and safety and to develop nuclear programmes.

Basic Studies in the Field of High-temperature Engineering

Basic Studies in the Field of High-temperature Engineering

Second Information Exchange Meeting: Paris, France 10-12 October 2001 You do not have access to this content

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22 May 2002
9789264175891 (PDF) ;9789264197961(print)

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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.

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Table of Contents

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. Haas, R. Conrad, M. Burghartz, and J.L. Kloosterman
-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
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
-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
-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
List of Participants

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