Graduated from the Slovak University of Technology in Bratislava (Nuclear and Physical Engineering) in 2018. Since then, he has been working in VUJE, a.s. as a researcher and analyst at the division of Nuclear Safety, Research and Development. His main activities are focused on thermo-hydraulic analyses of severe accidents using MELCOR code.
He is an expert in development of computational models of nuclear fuel for neutronic codes (SCALE) and thermo-hydraulic codes using MELCOR code. He performed thermo-hydraulic analysis of reactor VVER 440/213 pressure vessel via simulation software ANSYS - CFD. He is a member of team responsible for commissioning of NPP MO3, 4.