In this work, a single step of coupled calculations for a fuel rod of IPR-R1 TRIGA was performed. The used me-thodology allowed to simulate the fuel pin behavior in steady-state mode for different power levels. The aim of this paper is to present a practical approach to perform coupled calculations between neutronic (Monte Carlo) and thermal-hydraulic (CFD) codes. For this purpose, is necessary to evaluate the influence of the water thermal-physical properties temperature variations on keff parameter. Besides that, Serpent Nuclear Code was used for the neutronics evaluation, while OpenFOAM was used for thermal-hydraulics. OpenFOAM si- mula-tions were made by using a modified chtMultiRegionFoam solver, developed to read Serpent output correctly. The neutronic code was used without any modifications. The results shows that this coupled calculations were consistent and that leads to encouraging further methodology development and its use for full core simulation. Also, the results shows good agreement with calculations performed using other version of OpenFOAM and Milonga as neutronic code.

The study of the human factor began in 1918 and underwent great expansion during the world War II, becoming an integral discipline of engineering in late 1945. The purpose of the human factor is to align technological resources with human abilities and limitations. In this way, the study becomes a tool to predict limitations that the user can demonstrate and correct before any operational failure occurs. Attention to the influence of the human factor within nuclear safety requirements came especially after the accident at Three Mile Island. According to official reports, the accident was due to human, institutional and mechanical failures, where the main cause was operator errors. The International Atomic Energy Agency (IAEA) considers the study of the human factor an integral part of safety factors related to organizational effectiveness and related to management, according to the document Periodic Safety Review for Research Reactors. This document is a security review that will support the answers to one of the requirements for granting Permanent Operation Authorization for the TRIGA IPR-R1 reactor, located in Belo Horizonte, Brazil. In this way, the compliance of competence and qualification of the reactor operators will be addressed. The qualification of the operators will be analyzed, if the position occupied is part of the training area, and if the level of personnel is consistent with the demands of ensuring safety and reliability. The document The Management System for Nuclear Installations, created by the IAEA, will be used as an evaluative criterion. The review of technical skills reinforces the requirements for the development of new operators and strengthens programs to encourage the improvement of technical skills.