HTGR Knowledge Base

Conference Article: Experimental study on structural integrity of oxidized support post for HTTR

Ishihara, M.; Iyoku, T.; Shiozawa, S. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment); Miki, T. (Fuji Electric Co. Ltd., Tokyo (Japan)); Takikawa, N. (Kawasaki Heavy Industries Ltd, Tokyo (Japan))

Abstract

The compressive fracture test of the core support post, which locates below the core of the High Temperature Engineering Test Reactor (HTTR), was carried out using oxidized half-scale post specimens. Test specimens were oxidized in an air environment at three levels of oxidation temperatures. In this paper, the fracture load obtained from the test was found to be much greater than the design seismic load postulated in the HTTR. The fracture load ratio decrease due to oxidation was in a good agreement between the test and the analysis in which the stress concentration fracture was considered at the contact region of the support post and the seat.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Technical committee meeting on response of fuel, fuel elements and gas cooled reactor cores under accidental air or water ingress conditions. Beijing (China). 25-27 Oct 1993
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--784, pp:25-31