Basic Studies in the Field of High-temperature Engineering Second Information Exchange Meeting: Paris, France 10-12 October 2001
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-temperatu...
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| Autores Corporativos: | , |
| Formato: | Libro electrónico |
| Idioma: | Inglés |
| Publicado: |
Paris :
OECD Publishing
2002.
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| Colección: | Nuclear Science,
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| Materias: | |
| Ver en Biblioteca Universitat Ramon Llull: | https://discovery.url.edu/permalink/34CSUC_URL/1im36ta/alma991009706036106719 |
Tabla de Contenidos:
- Foreword; CONTENTS; Executive Summary; OPENING SESSION; Welcome Address; Opening Address; SESSION I Overviews of High-temperature Engineering Research in EachCountry and Organisation; Research Activities on Hish-Temperature Gas-cooled Reactors (HTRs) in the 5th Euration RTD Framework Programme; Update on IAEA High-Temperature Gas-cooled Reactor Activities; Present Status of the Innovative Basic Research on High-Temperature Engineering using the HTTR; Present Status in the Netherlands of Research Relevant to High-Temperature Gas-cooled Reactor Design
- Current Status of High-Temperature Engineering Research in FranceOverview of High-Temperature Reactor Engineering and Research; The Contribution of UK Organisations in the Development of New High-Temperature Reactors; SESSION II Improvement in Material Properties by High-temperature Irradiation; Improvement in Ductility of Refractory Metals by Neutron Irradiation; Effects of Superplastic Deformation on the Thernal and Mechanical Properties of 3Y-TZP Ceramics (Review); Development of an Innovative Carbon-based Ceramic Material: Application in High-Temperature, Neutron and Hydrogen Environment
- A Carbon Dioxide Partial Condensation Cycle for High-Temperature ReactorsSESSION III Development of In-core Material Characterisation Methodsand Irradiation Facility; Development of the I-I Type Irradiation Equipment for the HTTR; Application of Optical Diagnostics in High-Temperature Gas-cooled Systems; Measurement Method of In-core Neutron and Gamma-ray Distributions with Scintillator Optical Fibre Detector and Self-Powered Detector; Development of In-core Test Capabilities for Material Characterisation
- Application of Work Function Measuring Technique to Monitoring/Characterisation of Material Surfaces under IrradiationDevelopment of High-temperature Irradiation Techniques Utilising the Japan Materials Testing Reactor; SESSION IV Basic Studies on Behaviour of Irradiated Graphite/Carbon andCeramic Materials Including their Composites under both Operationand Storage Conditions; Investigation of High-Temperature Reactor (HTR) Materials; Radially Keyed Graphite Moderator Cores: An Investigation into the Stability of Finite Element Models
- Understanding of Mechanical Properties of Graphite on the Basis of Mesoscopic Microstructure (Review)Advanced Graphite Oxidation Models; Arradiation Creep in Graphite - A Review; An Analysis of Irradiation Creep in Nuclear Graphites; Planning for Disposal of Irradiated Graphite: Issues for the New Generation of HTRs; Status of IAEA International Database on Irradiated Graphite Properties with Respect to HTR Engineering Issues; SESSION V Basic Studies on HTGR Fuel Fabrication and Performance; Evidence of Dramatic Fission Product Release from Irradiated Nuclear Ceramics
- Method Reactor Tests of HTGR Fuel Elements at an Impulse Loading
