Performance of ZrC-Coated Particle Fuel in Irradiation and Postirradiation Heating Tests

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.