Published July 2018 | Version v1
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Excellent feature of Japanese HTGR technologies

Creators

  • 1. Japan Atomic Energy Agency, Sector of Nuclear Science Research, HTGR Hydrogen and Heat Application Research Center, Oarai, Ibaraki (Japan)
  • 2. Japan Atomic Energy Agency, Sector of Fast Reactor and Advanced Reactor Research and Development, Department of HTTR, Oarai, Ibaraki (Japan)

Description

Research and development on High Temperature Gas-cooled Reactor (HTGR) in Japan started since late 1960s. Japan Atomic Energy Agency (JAEA) in cooperation with Japanese industries has researched and developed system design, fuel, graphite, metallic material, reactor engineering, high temperature components, high temperature irradiation and post irradiation test of fuel and graphite, high temperature heat application and so on. Construction of the first Japanese HTGR, High Temperature engineering Test Reactor (HTTR), started in 1990. HTTR achieved first criticality in 1998. After that, various test operations have been carried out to establish the Japanese HTGR technologies and to verify the inherent safety features of HTGR. This report presents several system design of HTGR, the world-highest-level Japanese HTGR technologies, JAEA's knowledge obtained from construction, operation and management of HTTR and heat application technologies for HTGR. (author)

Availability note (English)

Available from JAEA; DOI: https://doi.org/10.11484/jaea-technology-2018-004

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Additional details

Identifiers

DOI
10.11484/jaea-technology-2018-004;

Publishing Information

Imprint Pagination
190 p.
Report number
JAEA-Technology--2018-004

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
50009533
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COATED FUEL PARTICLES; COGENERATION; FISSION PRODUCT RELEASE; FUEL ASSEMBLIES; GAS TURBINES; HEAT EXCHANGERS; HELIUM; HTTR REACTOR; HYDROGEN PRODUCTION; REACTOR DESIGN; REACTOR MAINTENANCE; TEST REACTORS
Descriptors DEC
DESIGN; ELEMENTS; ENRICHED URANIUM REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FLUIDS; FUEL PARTICLES; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MACHINERY; MAINTENANCE; NONMETALS; OPERATION; POWER GENERATION; RARE GASES; REACTOR LIFE CYCLE; REACTOR OPERATION; REACTORS; RESEARCH AND TEST REACTORS; STEAM GENERATION; TEST FACILITIES; TURBINES; TURBOMACHINERY

Optional Information

Notes
131 refs., 101 figs., 33 tabs.