Fuel rod performance is an important part of the modern reactor core analysis codes. In order to test and confirm the reactor core safety, one who performs the core design needs of some hypothetical scenarios calculation conducted with the fuel rod failure accidents. Two types of failure accidents are commonly considered: extra reactivity insertion accident (RIA) and loss of coolant accident (LOCA). The accidents could lead to the pellet-cladding mechanical interaction with a large cladding deformation and burst on the last simulation stage. Accurate simulation of the large cladding deformations requires the two- or three- dimensional modeling that is able to catch the real cladding reshaping and properly predict its critical stress and strain points. In our research, we compare the one-dimensional model FRACAS-I and finite element model FEA provided by the fuel performance analysis code FRAPTRAN. We calculate the accident benchmark using the REP-Na8 and compare the thermal-mechanical response between both models. The calculation shows a significant difference between the results of thermal radial gap, cladding hoop stress and cladding hoop strain. The FEA's results show similar response to the physical experiment data. We recommend that FEA mechanical model is suitable for further entire core simulation analysis.