Fission-gas release from pyrolytic-carbon-coated uranium carbide particles was studied as part of a fuel-development program for gas-cooled reactors. The particles were contained in a test capsule between concentric cylinders of porous graphite and were heated by fission heat. A small flow of helium was used to sweep the fission gas from the test capsule. Uranium carbide particles coated with three types of pyrolytic carbon (laminar, columnar, and duplex), as well as uncoated uranium carbide particles, were irradiated at temperatures up to 1800 F. The steady-state fission-gas release rates were measured as a function of temperature and burnup. All three coating types greatly reduced the fission-gas release rate from uranium carbide particles; the duplex coating was much better than the laminar or the columnar coatings. Post-irradiation examination revealed less than 0.1% broken coatings for the duplex coating. A radiation-induced reaction zone was observed at the fuel/coating interface for all three types. A correlation was made between the number of broken coatings and fission-gas release rate.