Studies on the core-support carbon material for VHTR, (1)
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
To obtain information of core-support carbon material for VHTR, thermal conductivity and electrical resistivity of three domestic carbon blocks were measured. Results indicated the need for development of carbon material with lower thermal conductivity for VHTR. These two were also measured of the samples heat-treated between 10000C and 30400C for one hour. Thermal conductivity increased with heat-treatment above 12000C and resistivity stayed constant between 15000C and 20000C. The results should be useful in choosing the final heat-treatment temperature in carbon material production. The changes of Lorentz number with heat treatment were classified into three heat-treatment temperature regions of below 15000C, 15000C - 25000C, and above 25000C; the results are interpreted with a graphitization model. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
11543608.pdf
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Additional details
Additional titles
- Subtitle (English)
- Changes of thermal conductivity and electrical resistivity due to heat-treatment
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- JAERI-M--8551
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 11543608
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ELECTRIC CONDUCTIVITY; EXPERIMENTAL DATA; GRAPHITE; GRAPHS; HEAT TREATMENTS; REACTOR CORES; TABLES; TEMPERATURE DEPENDENCE; THERMAL CONDUCTIVITY; VERY HIGH TEMPERATURE; VHTR REACTOR
- Descriptors DEC
- CARBON; DATA; DATA FORMS; ELECTRICAL PROPERTIES; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INFORMATION; NONMETALS; NUMERICAL DATA; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES