Abstract: As the core component of the reactor system, the performance of fuel rod is very important for the safe operation of the reactor. It is of great significance to accurately predict the behavior change of fuel rod under transient accident for reactor safety analysis. Fuel behavior models applicable to reactivity insertion accident (RIA) and loss of coolant accident (LOCA) were implemented in fuel rod performance analysis code BEEs, which was developed based upon the finite element platform MOOSE, and validations of separate models against experimental data were conducted. Integral analyses of CABRIRIA Na2 and NRULOCA MT4 tests were conducted to validate the modeling capacity of BEEs during RIA and LOCA, respectively. The results show that the overall modeling capacity of BEEs code for PWR fuel rod during transient accidents can be verified, predictions by BEEs code of fuel temperature, mechanical deformation and internal pressure in integral analyses are reasonable, which indicates the extended models of elastic-plasticity, high-temperature creep, phase transition, high-temperature oxidation and failure criteria of cladding are applicable to the performance analysis of fuel rod under transient accidents further.