Basic studies in the field of high-temperature engineering : second information exchange meeting, Paris, France, 10-12 October 2001 / co-organized by the Japan Atomic Energy Research Institute.

Format:

Book

Contributor:

Nihon Genshiryoku Kenkyūjo.

Series:

Nuclear science

Language:

English

Subjects (All):

Gas cooled reactors--Congresses.

Gas cooled reactors.

Heat resistant materials--Congresses.

Heat resistant materials.

High temperatures--Congresses.

High temperatures.

Genre:

Conference papers and proceedings.

Physical Description:

356 pages : illustrations ; 28 cm.

Place of Publication:

Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, [2002]

Summary:

These proceedings of an October 2001 meeting provide an overview of research on the improvement of material properties for high- temperature, gas-cooled reactor (HTGR) applications, in-core monitoring methods and properties of irradiated graphite, and HTGR fuel fabrication and performance. Specific topics include improvement in ductility of refractory metals by neutron irradiation, development of in-core test capabilities for material characterization, advanced graphite oxidation models, evidence of dramatic fission product release from irradiated nuclear ceramics, and an analysis of irradiation creep in nuclear graphites. There is no subject index. Annotation copyrighted by Book News, Inc., Portland, OR

Contents:

Opening Session 11

Session I Overviews of High-temperature Engineering Research in Each Country and Organisation / Chair: W. von Lensa 17

Research Activities on High-temperature Gas-cooled Reactors (HTRs) in the 5th EURATOM RTD Framework Programme / J. Martin-Bermejo, M. Hugon, G. Van Goethem 19

Update on IAEA High-temperature Gas-cooled Reactor Activities / J. Kendall, M. Methnani 31

Present Status of the Innovative Basic Research on High-temperature Engineering using the HTTR / 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, S. Shiozawa 39

Present Status in the Netherlands of Research Relevant to High Temperature Gas-cooled Reactor Design / J.C. Kuijper, A.I. van Heek, J.B.M. de Haas, R. Conrad, M. Burghartz, J.L. Kloosterman 51

Current Status of High-temperature Engineering Research in France / D. Hittner, F. Carre, J. Roualt 69

Overview of High-temperature Reactor Engineering and Research / K. Kugeler, P-W. Phlippen, M. Kugeler, H. Hohn 77

The Contribution of UK Organisations in the Development of New High-temperature Reactors / A.J. Wickham, I.M. Coe, P.J. Bramah, T.J. Abram 91

Session II Improvement in Material Properties by High-temperature Irradiation / Chairs: T. Shikama, B. Marsden 101

Improvement in Ductility of Refractory Metals by Neutron Irradiation / H. Kurishita 103

Effects of Superplastic Deformation on Thermal and Mechanical Properties of 3Y-TZP Ceramics (Review) / M. Ishihara, T. Shibata, S. Baba, T. Hoshiya, C. Wan, Y. Motohashi 113

Development of an Innovative Carbon-based Ceramic Material: Application in High-temperature, Neutron and Hydrogen Environment / C.H. Wu 125

A Carbon Dioxide Partial Condensation Cycle for High-temperature Reactors / T. Nitawaki, Y. Kato 133

Session III Development of In-core Material Characterisation Methods and Irradiation Facility / Chairs: C. Vitanza, M. Yamawaki 143

Development of the I-I Type Irradiation Equipment for the HTTR / T. Shibata, T. Kikuchi, S. Miyamoto, K. Ogura, Y. Ishigaki 145

Application of Optical Diagnostics in High-temperature Gas-cooled Systems / T. Shikama, M. Narui, T. Kakuta, M. Ishitsuka, K. Hayashi, T. Sagawa, T. Hoshiya 153

Measurement Method of In-core Neutron and Gamma-ray Distributions with Scintillator Optical Fibre Detector and Self-powered Detector / C. Mori, A. Uritani, T. Kakuta, M. Katagiri, T. Shikama, M. Nakazawa, T. Iguchi, J. Kawarabayashi, I. Kimura, H. Kobayashi, S. Hayashi 161

Development of In-core Test Capabilities for Material Characterisation / C. Vitanza 167

Application of Work Function Measuring Technique to Monitoring/Characterisation of Material Surfaces under Irradiation / G-N. Luo, T. Terai, M. Yamawaki, K. Yamaguchi 177

Development of High-temperature Irradiation Techniques Utilising the Japan Materials Testing Reactor / M. Narui, T. Shikama, M. Yamasaki, H. Matsui 191

Session IV Basic Studies on Behaviour of Irradiated Graphite/Carbon and Ceramic Materials Including their Composites under both Operation and Storage Conditions / Chairs: B. McEnaney, A. Wickham 201

Investigation of High-temperature Reactor (HTR) Materials / D. Buckthorpe, R. Couturier, B. van der Schaaf, B. Riou, H. Rantala, R. Moormann, F. Alonso, B-C. Friedrich 203

Radially Keyed Graphite Moderator Cores: An Investigation into the Stability of Finite Element Models / W.R. Taylor, M.D. Warner, G.B. Neighbour, B. McEnaney, S.E. Clift 215

Understanding of Mechanical Properties of Graphite on the Basis of Mesoscopic Microstructure (Review) / M. Ishihara, T. Shibata, T. Takahashi, S. Baba, T. Hoshiya 225

Advanced Graphite Oxidation Models / R. Moormann, H-K. Hinssen 243

Irradiation Creep in Graphite - A Review / B.J. Marsden, S.D. Preston 255

An Analysis of Irradiation Creep in Nuclear Graphites / G.B. Neighbour, P.J. Hacker 269

Planning for Disposal of Irradiated Graphite: Issues for the New Generation of HTRs / B. McEnaney, A.J. Wickham, M. Dubourg 281

Status of IAEA International Database on Irradiated Graphite Properties with Respect to HTR Engineering Issues / P.J. Hacker, B. McEnaney, A.J. Wickham, G. Haag 293

Session V Basic Studies on HTGR Fuel Fabrication and Performance / Chairs: J. Kuijper, R. Moormann 305

Evidence of Dramatic Fission Product Release from Irradiated Nuclear Ceramics / L. Thome, A. Gentils, F. Garrido, J. Jagielski 307

Method of Reactor Tests of HTGR Fuel Elements at an Impulse Loading / A. Chernikov, V. Eremeev, V. Ivanov 315

Gas Reactor TRISO-coated Particle Fuel Modelling Activities at the Idaho National Engineering and Environmental Laboratory / D. Petti, G. Miller, J. Maki, D. Varacalle, J. Buongiorno 323.

Notes:

Includes bibliographical references.

ISBN:

9264197966

OCLC:

50191461