To study the dynamic strain aging behavior of Zr-0.4Sn-1.5Nb-0.2Fe sample tube for nuclear fuel cladding in the range of pressurized water reactor (PWR) operation temperature, the tensile tests of the tube specimens, which had been finally heat-treated at $470^{circ}C;and;510^{circ}C$, had been carried out with the strain rate $1.67{ imes}10^{-2}/s;and;8.33{ imes}10^{-5}/s$ at the various temperatures from room temperature to $500^{circ}C$. It was observed that the elongation of the specimens got shortened as the temperature increased from $200^{circ}C;to;340^{circ}C$. The specimens that were finally heat-treated at $470^{circ}C$ showed a plateau more remarkably on the plot of yield strength-temperature than those heat-treated at $510^{circ}C$. In the range of $310sim400^{circ}C$, the strain rate sensitivity of the specimens finally heat-treated at $510^{circ}C$ was $30.4\%sim33.7\%$ lower but the work hardening exponent index of the specimens was a little higher than that without dynamic strain aging effect.