Japan Atomic Energy Agency(JAEA) has developed the High Temperature Engineering Test Reactor (HTTR), the first HTGR in Japan. The reactor power is 30MW and the outlet helium-gas temperature is 950C at the maximum. HTTR uses block type fuel element. In the presentation at the seminar, the outline of the structure of HTTR, development history, safety features will be presented.
The recent progress in multiphase science and technology has made a considerable impact on nuclear reactor thermal-hydraulics. However, the needs for obtaining solutions to a variety of practical questions have had both pros and cons. The former have been reflected in the role of needs as an obvious research stimulation factor, the latter have been due to fact that the urgency of producing results often limited systematic investigations of the underlying physics.
9:00-12:00 Presentations concerning HTGR cogeneration system development
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