The TRIGA IPR-R1, a pool type research reactor located at the Nuclear Technology Development Center (CDTN -Centro de Desenvolvimento da Tecnologia Nuclear) in Campus UFMG, was modeled with the Serpent 2.1.32 and SCALE 6.2.4. The goal is to assess the nuclear data sensitivity of the multiplication factor to the different codes using some neutron cross-section libraries, namely: ENDF/B-VII.1, ENDF/B-VIII.0, JEFF-3.1.3 and JEFF-3.3. The partial results show that Serpent overestimates the multiplication factor of the system when using both JEFF and ENDF libraries at CZP conditions (TF = 300K). While at HFP conditions (TF = 373K), Serpent using JEFF-3.1.3 and ENDF/B-VIII.0 presented larger keff values than SCALE using ENDF/B-VII.1. In general, the different libraries presented good agreement and in future works, burnup calculations will be performed to further study the impact of these libraries in the modelled reactor.