Computational Codes for Nuclear Reactors

Code 1098I
Credits 6

Learning outcomes

- FORTRAN programming fundamentals;
- Brief overview of balance equations and turbulence models for CFD codes applications;
- Practical examples of problems of interest for nuclear engineering solved by the ANSYS-FLUENT code;
- Study of discrete systems: the structural matrix calculation.
o Basic concepts of structural matrix analysis: discrete systems.
o Method of displacement.
o Matrix of stiffness, constraints, applied loads, boundary conditions.
- The finite element method
o Introduction to Finite Element codes
o Mathematical formulation of the finite element method.
o Discretization of continuum, elements, shape functions.
o Main types of elements for 1D, 2D, 3D problems: rods, beams, plate/flat and shell, axisymmetric elements, and solid elements.
o Linear and nonlinear Analysis.
- Implementation of the method
o Overview of FEM codes.
o Pre-processing phase: model definition, definition of the elements for the discretization, materials behavior (equation of state), methods and issues related to the discretization, boundary conditions: loads, constraints and user subroutine.
o Solution phase: load case and options, iterative methods and methods to control the solution.
o Post-processing phase: visualization, interpretation and analysis of the main results.
- Applications (Exercises with FEM code)
o Problems of structural elastic, elastic-plastic, thermal and thermo-mechanical, dynamic, etc.
- Short overview of the deterministic and stochastic approach to the neutron calculations.
- The cross sections: multi-groups libraries and continuous-energy libraries.
- Use of homemade and open source codes to solve a reference problem with the diffusion and transport approximations.
- Comparison of the results: accuracy and computational time.