TECHNOLOGIES IN NUCLEAR FUSION EXPERIMENTAL FACILITIES
Overview on today power supply systems for tokamaks in view of DEMO. Basics of superconductivity, Superconducting materials for nuclear fusion. DTT proposal. Fusion reactors fuel cycle. Main technologies and processes of the fusion fuel cycle. Membrane processes and technologies in the fuel cycle. Overview of the fuel cycle on existing tokamaks and next nuclear fusion experimental devices.

MECHANICAL ENGINEERING IN TOKAMAKS
Applications of ANSYS and ANSYS MAXWELL for the solution of multi-physics 3D PDE problem in experimental nuclear fusion facilities.

INTRODUCTION TO PLASMA WALL PROTECTION
First Wall: theory and applications; Divertor: theory and applications.

NUMERICAL METHODS FOR PLASMA ENGINEERING
Optimization methods; Free and Constrained Simplex; Free and Constrained Gradient methods; Free and Constrained Linear programming; Free and Constrained Quadratic Programming. Application of Optimization Methods in Matlab; Application of Quadratic Programming to the optimization of the divertor coils currents of the JET tokamaks for the design of high plasma Flux Expansion experiments.

INTRODUCTION TO CONTROL ENGINEERING FOR NUCLEAR FUSION EXPERIMENTAL FACILITIES
Dynamic systems and mathematical models. Block diagrams. Control system architectures (open loop, closed loop). Mathematical model of simple systems. Linear dynamical systems in the time domain. Equilibrium. Linearization. Laplace Transformation and Anti-Transofrmation. Pulse response and convolution integrals. Transfer function: definition and properties. Poles, zeros and gains. Canonic responses of 1st and 2nd order systems. Frequency response: definition, meaning and relations with the transfer function. Graphical representation of the frequency response: Bode and polar diagrams. Stability and stability criteria. General properties of a feedback system. Static and dynamic performances.

1 - Lectures notes

2 - Wesson, Tokamaks, Oxford University Press

3 - Pucella, Segre, Fisica dei plasmi, Zanichelli

4 - Ariola, Pironti, Magnetic Control and Tokamak Plasmas, Springer

1. INTRODUCTION AND EQUILIBRIUM CONFIGURATIONS. Introduction to energy fusion. Magnetic flux e field: normalized flux and radius coordinates. Equilibrium of an axisymmetric toroidal configuration; derivation of Grad-Shafranov equation; plasma shape in a tokamak.
2. INTRODUCTION TO PLASMA PHYSICS. Classification of plasmas, Debye length, collisions between charged particles, collisional slowing-down, plasma resistivity. Fusion reactor scheme, power balance, Lawson criterion, Ideal ignition temperature.
3. PLASMA DIAGNOSTICS, CIRCUIT MODELS AND HEATING. General description of main plasma diagnostics. Magnetic diagnostics. Circuit models (for plasma, poloidal field coils and conducting structures); transformers; plasma current induction; magnetic flux balance; time evolution of tokamak scenarios; tokamak time scales. Introduction to plasma current, position, shape control systems: plasma radial position and current control, vertical stabilization of elongated plasma. Eddy currents and magnetic forces. Overview of Plasma Heating and Current Drive.
4. NEUTRONIC. Basic neutron physics and breeding concept, introduction to neutron transport, neutronics and activation calculations. Introduction to neutron sources and material damage.
5. DISRUPTIONS, VDE, PLASMA SCENARIO, MAGNETIC DIAGNOSTICS. Review of Circuit models for plasma, poloidal field coils and conducting structures, Transformers, Plasma current induction, Magnetic flux balance. Time evolution of a tokamak scenario, Tokamak time scales, Disruptions and VDE, Eddy and halo currents, DTT VDEs. MAXFEA code: equilibrium and disruptions.
6. POWER EXHAUST ISSUES: PHYSICS AND TECHNOLOGY. Fundamental physics relations in the SOL, Validating our understanding in present devices. Numerical tools, Making the step to larger devices. Design of Actively Cooled Plasma Facing Components (PFCs), thermos-hydraulic design of a divertor plasma facing components. Preliminary investigation on W foams as protection strategy for advanced PFCs.
7. THE ERA OF THE ATOM: ONE CENTURY AHEAD THE BOHR MODEL (seminar).
8. ADDITIONAL HEATING SCHEMES FOR TOKAMAKS. Scope of additional heatings, additional heating techniques, NBI, ICRH, ECRH, Task for HCD systems.

Lecture Notes and presentations
Wesson, Tokamaks, Oxford University Press
Pucella, Segre, Fisica dei plasmi, Zanichelli
Ariola, Pironti, Magnetic Control and Tokamak Plasmas, Springer