Design of high temperature Engineering Test Reactor (HTTR)
Creators
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Description
Construction of High Temperature Engineering Test Reactor (HTTR) is now underway to establish and upgrade basic technologies for HTGRs and to conduct innovative basic research at high temperatures. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW in thermal output and outlet coolant temperature of 850degC for rated operation and 950degC for high temperature test operation. It is planned to conduct various irradiation tests for fuels and materials, safety demonstration tests and nuclear heat application tests. JAERI received construction permit of HTTR reactor facility in February 1990 after 22 months of safety review. This report summarizes evaluation of nuclear and thermal-hydraulic characteristics, design outline of major systems and components, and also includes relating R and D result and safety evaluation. Criteria for judgment, selection of postulated events, major analytical conditions for anticipated operational occurrences and accidents, computer codes used in safety analysis and evaluation of each event are presented in the safety evaluation. (author)
Availability note (English)
MF available from INIS under the Report Number.
Files
System files
(509.4 kB)
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Additional details
Identifiers
- DOI
- 10.11484/jaeri-1332;
Publishing Information
- Imprint Pagination
- 268 p.
- Report number
- JAERI--1332
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 27002401
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COATED FUEL PARTICLES; FUEL ASSEMBLIES; HTTR REACTOR; MOCKUP; PROCESS HEAT REACTORS; RADIOACTIVE WASTE STORAGE; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR CHARGING MACHINES; REACTOR CONTROL SYSTEMS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR EXPERIMENTAL FACILITIES; REACTOR FUELING; REACTOR INSTRUMENTATION; REACTOR LICENSING; REACTOR OPERATION; REACTOR SAFETY; TEMPERATURE RANGE 1000-4000 K
- Descriptors DEC
- ACCIDENTS; CONTROL SYSTEMS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; LICENSING; MANAGEMENT; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; STORAGE; STRUCTURAL MODELS; TEMPERATURE RANGE; WASTE MANAGEMENT; WASTE STORAGE