Published February 2004
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Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2002)
Description
The HTTR (High Temperature Engineering Test Reactor) with the thermal power of 30 MW and the reactor outlet coolant temperature of 850/950degC is the first high temperature gas-cooled reactor (HTGR) in Japan, which uses coated fuel particle, graphite for core components, and helium gas for primary coolant. In December 2001, the thermal power of 30 MW and the reactor outlet coolant temperature of 850degC was attained. JAERI received the certificate of pre-operation test, that is, the commissioning licence for the HTTR in March 2002. This report summarizes operation, tests, maintenance, radiation control, and construction of components and facilities for the HTTR as well as R and D on HTGRs for FY2002. (author)
Availability note (English)
Available from INIS in electronic form; Also available from JAEA; URL: http://jolisf.tokai-sc.jaea.go.jp/pdf/rev/JAERI-Review-2003-043.pdfFiles
36116927.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 102 p.
- Report number
- JAERI-Review--2003-043
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36116927
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- CONTROL; EVALUATION; HTTR REACTOR; INTERNATIONAL COOPERATION; PERFORMANCE; POWER RANGE 10-100 MW; PROGRESS REPORT; RADIATION DOSES; REACTOR MAINTENANCE; REACTOR OPERATION; RESEARCH PROGRAMS; TESTING
- Descriptors DEC
- COOPERATION; DOCUMENT TYPES; DOSES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MAINTENANCE; MEGAWATT POWER RANGE; OPERATION; POWER RANGE; REACTORS; RESEARCH AND TEST REACTORS
Optional Information
- Notes
- 7 refs., 30 figs., 12 tabs.; This record replaces 35074211