The main objective of the course is to provide the students with the knowledge of the fundamental (theoretical and practical) aspects of the software codes currently used in the nuclear engineering field, the methodologies and tools they implement and knowledge of the data analysis techniques.
The student will be involved in the resolution of different practical exercises. Ansys Design Modeler, Ansys Meshing, Ansys FLUENT and RELAP5\mod3.3 codes will be used for solving thermal-hydraulics problems. The basic theory related to turbulence models and balance equations applied in CFD and System Thermal Hydraulic codes will be discussed. For what concerns the problems of neutron transport, information will be provided in general about the different kinds of computational codes used in the field, while in particular the Monte Carlo code OpenMC will be used to study a specific problem of neutron transport. Numerical and theoretical studies of the finite element method and its application FEM codes (such as MSC.MARC; ANSYS, etc.) will be considered for thermo-mechanical problems. As for FEM, students will be able to perform structural analysis in simple or complex geometry.