HTGR Knowledge Base

Conference Article: Test programmes of HTTR for future generation HTGRs

Kunitomi, K.; Tachibana, Y.; Takeda, T.; Saikusa, A.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan))

Abstract

Test programs of the High Temperature Engineering Test Reactor (HTTR) for future generation High Temperature Gas-Cooled Reactors (HTGRs) have been established considering design and development status of HTGRs in Japan and the world. Test programs are divided into six categories, thermal hydraulics, fuel, safety, high temperature components, core physics and control-instrumentations. All programs are related to the technology of future generation HTGRs and will be submitted to a new Coordinated Research Program (CRP) so that all participants from the world in test programs of the HTTR can use measured data for their future generation.HTGRs. This paper describes test programs of the HTTR for the development of future generation HTGRs after explanation of a future generation HTGR in Japan.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Technical committee meeting on high temperature gas cooled reactor technology development. Johannesburg (South Africa). 13-15 Nov 1996.
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--988, pp:359-371