Basic Studies in the Field of High-temperature Engineering [electronic resource]: Second Information...
Basic Studies in the Field of High-temperature Engineering [electronic resource]: Second Information...
Basic Studies in the Field of High-temperature Engineering [electronic resource]: Second Information Exchange Meeting: Paris, France 10-12 October 2001 / Organisation for Economic Co-operation and Development and Nuclear Energy Agency
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Author / Creator
Publisher
Paris : OECD Publishing, 2002.
Alternative title
Date
2002.
Record Identifier
MMS ID
Language
English
Formats
Physical Description
Physical content
1 online resource (360 p.)
Content type
text
Media type
computer
Carrier type
online resource
Contents
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; Upda...
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; Imp...
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 Sys...
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 M...
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 G...
Method Reactor Tests of HTGR Fuel Elements at an Impulse Loading
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Scope and Contents
Summary
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 overv...
Alternative Titles
Full title
Basic Studies in the Field of High-temperature Engineering [electronic resource]: Second Information Exchange Meeting: Paris, France 10-12 October 2001 / Organisation for Economic Co-operation and Development and Nuclear Energy Agency
Variant title
BOOK
Authors, Artists and Contributors
Author / Creator
Author / Artists
Notes
General note
Nuclear Science, 19900643.
Description based upon print version of record.
Language note
English
Issued As
Nuclear Science (CKB)2590000000003067 1990-0643
Identifiers
Primary Identifiers
Record Identifier
74VK3lLao38Z
Permalink
https://devfeature-collection.sl.nsw.gov.au/record/74VK3lLao38Z
Other Identifiers
ISBN
1-280-03456-4
DDC
621.4834
MMS ID
991023942723702626
