Published October 1969
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High Temperature Radiation Induced Creep in Graphite
Description
The irradiation creep of graphite has been determined at 600, 800, 900 and 1200°C by successive irradiations in the High Flux Reactor Petten, of specially designed assemblies in which two or more graphites having differing shrinkage rates are used in opposition to provide tensile or compressive stress in a specimen. The experimental technique is described and the results are compared with the predicted calculated behaviour of the assemblies, Tensile Creep strain in excess of 2% have been obtained. Attempts are made to correlate the observed creep constants with other physical properties. (author)
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Additional details
Publishing Information
- Imprint Pagination
- 51 p.
- Report number
- DP-R--665
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54049093
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CREEP; DESIGN; FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; GRAPHITE; HFR REACTOR; HTGR TYPE REACTORS; IRRADIATION; STRAINS; STRESSES; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- CARBON; DEVELOPED COUNTRIES; ELEMENTS; ENRICHED URANIUM REACTORS; EUROPE; EVALUATION; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; MINERALS; NATIONAL ORGANIZATIONS; NONMETALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Notes
- Document from Juelich Preservation Project; 10 refs., 11 tabs., 12 figs.