The work aims to enable the finite element simulation technology to become a practical and effective research method, and then provide the theoretical basis for the design of high-performance reactor cladding materials and possible emergency measures under the LOCA (Loss of Coolant Accident). Based on COMSOL software, the temperature rise of typical zirconium alloy nuclear materials after induction heating and resistance heating under LOCA conditions was simulated herein. The results showed that the difference between the highest temperature, the average volume temperature and the surface center temperature increased with the rise of temperature. At transient temperature of 1200 ℃, the temperature difference was the highest, about 41 ℃. Under the condition of resistance heating, the highest temperature in volume, the center temperature in volume and the surface center temperature of the zirconium material almost coincided with one another in the whole heating stage, with the maximum difference of about 3 ℃. The difference between the average volume temperature, the average surface temperature and the surface center temperature of zirconium material was negative, and the maximum difference was about 30 ℃. It is found that both resistance heating and induction heating are suitable for the simulation of ultra-high temperature and ultra-fast temperature rise rate for cladding materials under LOCA conditions. However, due to the lag of resistance heating rate under actual working conditions, induction heating is recommended for subsequent simulation experiments. The relevant results can provide necessary theoretical basis for the design of high-performance reactor cladding materials.