Thermal cycle test of a full-scale graphite sleeve for use in the VHTR
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
A full-scale graphite sleeve which was made of the candidate graphite material IG-11 for a very high temperature gas-cooled reactor(VHTR), was tested by the application of a rapid heating and cooling to clarify its endurance for thermal shock. The graphite sleeve having inner diameter 36 mm, outer diameter 46 mm and length 550 mm was heated at an average heating rate of 80 0C per seconds to the maximum temperature of 2000 0C or 2200 0C and then the sleeve was cooled to 500 0C. The thermal cycle was repeated 500 in the case of the maximum temperature 2200 0C and 1000 in the case of 2000 0C. The dimensions, electric resistance and Young's modulus were measured at room temperature after the application of a fixed thermal cycle. The measurements were repeated at a fixed intervals. At the early stage of thermal cycle length expanded, electric resistance and Young's modulus decreased, and they were almost constant in the following thermal cycles. The results showed that the properties of the graphite sleeve were hardly changed due to the application of a rapid heating and cooling and its performance was almost unchamged. (author)
Availability note (English)
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17047598.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 22 p.
- Report number
- JAERI-M--85-162
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 17047598
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ELECTRIC CONDUCTIVITY; GRAPHITE; HIGH TEMPERATURE; MECHANICAL TESTS; SLEEVES; THERMAL CYCLING; THERMAL SHOCK; VERY HIGH TEMPERATURE; VHTR REACTOR; YOUNG MODULUS
- Descriptors DEC
- CARBON; ELECTRICAL PROPERTIES; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATERIALS TESTING; MECHANICAL PROPERTIES; NONMETALS; PHYSICAL PROPERTIES; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; TESTING; THERMAL REACTORS