Experiment in the making of U-ZrHx powder at Zr content variation for PWR reactor fuel has been carried out. At first, U-Zr ingots was made with Zr content of 35wt% (U-35Zr), 45wt% (U-45Zr) and 55wt% (U-55Zr). Then U-Zr ingots were used to make U-ZrHx powder through hydriding technique. Hydriding process carried out at temperatures of 450° C with vacuum pressure of 14.80884 x 10-3 psi and under hydrogen gas flowing for 10 hours. Then U-ZrHx powders were tested to determine the characteristics such as density, heat capacity, and morphology. The test results showed that the density of the U-ZrHx decrease with increasing Zr content. The density are 10.4256 g/cc, 8.000 g/cc respectively, and 7.0359 g / cc for U-35ZrHx, U-45ZrHx and U-55ZrHx alloy. The heat capacity test results showed that the highest heat capacity is achieved at U-45ZrHx alloy powder that measured up to temperature of 437° C that is equal to 0.37J/g.°C. When observed from the test temperature, indicate that the heat capacity value for each sample examination decrease with increasing the test temperature. Meanwhile, the powder morphology examination result showed that all the U-ZrHx powder sample have a flat shape, irregular and tend have the smaller particle with higher increasing the Zr content.