HTGR Knowledge Base

Conference Article: Characteristics of HTTR's startup physics tests

Nojiri, N.; Nakano, M.; Takeuchi, M.; Pohl, P.; Yamashita, K. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan))

Abstract

The High Temperature Engineering Test Reactor (HTTR) which is under construction by Japan Atomic Energy Research Institute (JAERI) is a graphite-moderated and helium gas-cooled reactor with an outlet temperature of 950 deg. C and a thermal output of 30MW. The first criticality is expected at the end of October 1997. The start-up physics tests (SPTs) are planned in the period from mid 1997 to the end of 1998. Characteristic items of the SPTs are: 1) Criticality approach. 2) Tests on a preliminary annual core. 3) Measurement of scram reactivity. 4) Excess reactivity test. 5) Measurements along with a 2-step-scram reactor shutdown procedure.

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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:333-343