Basic Studies in the Field of High-Temperature Engineering

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Editorial Reviews

From The Critics
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 c. Book News, Inc., Portland, OR
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Product Details

  • ISBN-13: 9789264197961
  • Publisher: Organization for Economic Cooperation and Development
  • Publication date: 6/28/2002
  • Series: Nuclear Science Ser.
  • Pages: 360

Table of Contents

Foreword 3
Executive Summary 9
Opening Session 11
Welcome Address 13
Opening Address 15
Session I Overviews of High-temperature Engineering Research in Each Country and Organisation 17
Research Activities on High-temperature Gas-cooled Reactors (HTRs) in the 5th EURATOM RTD Framework Programme 19
Update on IAEA High-temperature Gas-cooled Reactor Activities 31
Present Status of the Innovative Basic Research on High-temperature Engineering using the HTTR 39
Present Status in the Netherlands of Research Relevant to High Temperature Gas-cooled Reactor Design 51
Current Status of High-temperature Engineering Research in France 69
Overview of High-temperature Reactor Engineering and Research 77
The Contribution of UK Organisations in the Development of New High-temperature Reactors 91
Session II Improvement in Material Properties by High-temperature Irradiation 101
Improvement in Ductility of Refractory Metals by Neutron Irradiation 103
Effects of Superplastic Deformation on Thermal and Mechanical Properties of 3Y-TZP Ceramics (Review) 113
Development of an Innovative Carbon-based Ceramic Material: Application in High-temperature, Neutron and Hydrogen Environment 125
A Carbon Dioxide Partial Condensation Cycle for High-temperature Reactors 133
Session III Development of In-core Material Characterisation Methods and Irradiation Facility 143
Development of the I-I Type Irradiation Equipment for the HTTR 145
Application of Optical Diagnostics in High-temperature Gas-cooled Systems 153
Measurement Method of In-core Neutron and Gamma-ray Distributions with Scintillator Optical Fibre Detector and Self-powered Detector 161
Development of In-core Test Capabilities for Material Characterisation 167
Application of Work Function Measuring Technique to Monitoring/Characterisation of Material Surfaces under Irradiation 177
Development of High-temperature Irradiation Techniques Utilising the Japan Materials Testing Reactor 191
Session IV Basic Studies on Behaviour of Irradiated Graphite/Carbon and Ceramic Materials Including their Composites under both Operation and Storage Conditions 201
Investigation of High-temperature Reactor (HTR) Materials 203
Radially Keyed Graphite Moderator Cores: An Investigation into the Stability of Finite Element Models 215
Understanding of Mechanical Properties of Graphite on the Basis of Mesoscopic Microstructure (Review) 225
Advanced Graphite Oxidation Models 243
Irradiation Creep in Graphite - A Review 255
An Analysis of Irradiation Creep in Nuclear Graphites 269
Planning for Disposal of Irradiated Graphite: Issues for the New Generation of HTRs 281
Status of IAEA International Database on Irradiated Graphite Properties with Respect to HTR Engineering Issues 293
Session V Basic Studies on HTGR Fuel Fabrication and Performance 305
Evidence of Dramatic Fission Product Release from Irradiated Nuclear Ceramics 307
Method of Reactor Tests of HTGR Fuel Elements at an Impulse Loading 315
Gas Reactor TRISO-coated Particle Fuel Modelling Activities at the Idaho National Engineering and Environmental Laboratory 323
Session Summaries 339
Recommendations 349
List of Participants 351
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