Operation, test, research and development of the high temperature engineering test reactor (HTTR). FY2007
Description
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30MW of thermal power. The full power operation of 30MW was attained in December 2001, and then JAERI (JAEA) received the commissioning license for the HTTR in March 2002. Since 2002, we have carried out rated power operations, safety demonstration tests and several R and Ds, etc. In April 2004, the HTTR conducted the high-temperature test operation with outlet coolant temperature of 950degC. In fiscal year 2007, we have carried out long-term (30 days) operation to accumulate operational data for HTGR developments. Periodical inspections, exchange of filter of primary gas circulators and in-service inspection of the reactor pressure vessel were also conducted, and manufacturing of control rod for exchange was started. This report summarizes activities and results of HTTR operation, maintenance, and several R and Ds, which were carried out in the fiscal year 2007. (author)
Availability note (English)
Available from JAEA; DOI: https://doi.org/10.11484/jaea-review-2008-049
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 142 p.
- Report number
- JAEA-Review--2008-049
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 40024370
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- ENVIRONMENTAL PROTECTION; HTTR REACTOR; INTERNATIONAL COOPERATION; JAEA; ON-SITE INSPECTION; PROGRESS REPORT; QUALITY ASSURANCE; RADIATION PROTECTION; REACTOR COMMISSIONING; REACTOR COMPONENTS; REACTOR MAINTENANCE; REACTOR OPERATION; REACTOR SAFETY
- Descriptors DEC
- COMMISSIONING; COOPERATION; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INSPECTION; JAPANESE ORGANIZATIONS; MAINTENANCE; NATIONAL ORGANIZATIONS; OPERATION; REACTORS; RESEARCH AND TEST REACTORS; SAFETY
Optional Information
- Notes
- 3 refs., 40 figs., 20 tabs.