[en] Subcritical hybrid systems include Accelerator Driven Reactor Systems (ADS). In these systems charged particles (protons, ions, among others) produced by an accelerator induce spallation reactions in targets, in general, with high-Z materials, resulting in the production of neutrons that are used in a subcritical reactor core. These systems have been studied by the Department of Nuclear Engineering at UFMG since the last decade, for application in transmutation of nuclear waste and breeding fissile material. Other studies suggest the use of ADS to produce fissile fuel from fertile isotopes, using as fuel mixtures based on thorium for the production of ²³³U or, to a lesser extent, depleted uranium for the conversion of ²³⁸U into ²³⁹Pu. The Th/U cycle has aroused interest in recent decades due to the extensive known reserves and the need to replace in the long term, even partially, the use of uranium by another fuel. During the development of previous studies for ADS, the libraries available in the MCNPX 2.6.0 package were used. However, when producing new libraries with NJOY99.396 at full power for other hybrid systems in studies, it was verified that this system should be reevaluated. Additionally, it is shown that systems that use Th as fertile material are sensitive to the data libraries used. Therefore, starting from the open questions previously presented, the objective of this work is to evaluate a more adequate cross-section data library to be used in the studied ADS reactor with the use of thorium. The system will be analyzed under different temperatures. Neutronics parameters such as the effective multiplication factor k_eff, the reproduction factor η, thermal utilization factor f, the resonance escape probability p and the fast fission factor ϵ will be evaluated. The codes NJOY99.396 and MCNPX 2.6.0 will be used to generate cross-section data at different temperatures and to simulate the ADS system, respectively. The cross-section data libraries that will be analyzed are: ENDF/B-VII.1, ENDF/B-VIII, JEFF-3.2, JEFF-3.3, CENDL-3.2, JENDL-4.0, BROND-3.1 and TENDL-2019. (author)