[en] Since the utilization of high-density silicide fuels are now being expanded in research reactors, the behavior of these fuels under transient and accidental conditions are of big concern. The transient behavior of the low-enriched uranium (19.89 w/o) silicide miniature fuel plates have been studied by the irradiation in the Nuclear Safety Research Reactor (NSRR) in the Japan Atomic Energy Research Institute. The energy of 154 cal at maximum was deposited per unit gram of the silicide fuel quite promptly by pulse-irradiating in the NSRR, and realized the transient temperature increase up to 970degC. Major results obtained from experiment are: (1) At fuel temperatures below 400degC, the silicide fuel plates kept a good dimensional stability and intactness. Fuel deformation started beyond 400degC, and beyond the melting temperature of Al - 3 % Mg alloy cladding, 640degC, fuel plates were largely damaged showing a bowing up to 7 mm. (2) Despite the large degradation of the fuel at cladding temperatures around 970degC, no fuel fragmentation nor mechanical energy generation was observed. (author)