Performance of ZrC-coated particle fuel in irradiation and postirradiationheating tests

Journal Article · Sat Oct 31 23:00:00 EST 1992 · Journal of the American Ceramic Society; (United States)

DOI:https://doi.org/10.1111/j.1151-2916.1992.tb04375.x· OSTI ID:7140041

Ogawa, T; Fukuda, K; Kashimura, S; Tobita, T; Kobayashi, F; Kado, S; Miyanishi, H; Takahashi, I; Kikuchi, T ^[1]

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1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

This paper reports on the ZrC-coated UO[sub 2] particle which is a promising fuel for high-temperature gas-cooled reactors. Particle fuels with multiple layers of pyrolytic carbon and ZrC have been irradiation-tested to a maximum fast-neutron fluence exceeding 2 [times] 10[sup 25]/m[sup 2] (E [gt] 29 fJ). In-reactor fission-gas release measured at a burnup of 1.5 at.% was minimal. The failure fraction by postirradiation examination was null for all samples. The ZrC-coated particles at 4 at.% burnup were postirradiation heated to 2400[degrees]C/min without failure until after 6000 s at the maximum temperature. It was found that the ZrC layer could sustain a large strain at such high temperatures. The behavior is in strong contrast with that of SiC of standard Triso coating, which is brittle to very high temperatures.

• OSTI ID: 7140041
• Journal Information: Journal of the American Ceramic Society; (United States), Journal Name: Journal of the American Ceramic Society; (United States) Vol. 75:11; ISSN 0002-7820; ISSN JACTAW
• Country of Publication: United States
• Language: English

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