NUCLEAR FUSION |
Code
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119566 |
Language
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ENG |
Type of certificate
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Profit certificate
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Module: NUCLEAR FUSION - module 1
(objectives)
The course will provide the basics necessary to physical (module II) and engineering (module I) understanding of fusion nuclear energy systems covering topics from magnetic confinement and plasma physics to plasma surface interaction, reactor materials, control systems and mechanics. The main objectives are (a) knowledge and key aspects of engineering, technology and physics associated with the ' magnetic fusion energy, (b) identification of the main features nuclear fusion tokamak devices , (c) knowledge of the state of the international research (JET, EAST, ASDEX) and perspectives of fusion nuclear energy (next experimental machines as DTT, ITER and DEMO). The expected learning results are: (i) the knowledge of the theoretical contents of the course (Dublin descriptor n°1), (ii) the competence in presenting technical argumentation skills (Dublin descriptor n°2), (iii) autonomy of judgment (Dublin descriptor n°3) in proposing the most appropriate approach to argue the request and (iv) the students' ability to express the answers to the questions proposed by the Commission with language properties, to support a dialectical relationship during discussion and to demonstrate logical-deductive and summary abilities in the exposition (Dublin descriptor n°4).
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Language
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ENG |
Type of certificate
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Profit certificate
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Credits
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5
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Scientific Disciplinary Sector Code
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ING-IND/31
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Contact Hours
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40
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Type of Activity
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Related or supplementary learning activities
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Teacher
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CALABRO' Giuseppe
(syllabus)
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. TOKAMAK LOAD ASSEMBLY: FROM CONCEPTUAL DESIGN TO REALIZATION. Introduction. Toroidal Field Coil System. Poloidal Field Coil System. Vacuum Vessel. Divertor and First Wall. Cooling. Assembly maintenance (remote handling). Supply System. 5. NEUTRONIC. Basic neutron physics and breeding concept, introduction to neutron transport, neutronics and activation calculations. Introduction to neutron sources and material damage. 6. 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. 7. 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. 8. OVERVIEW ON TODAY POWER SUPPLY SYSTEMS FOR TOKAMAKS IN VIEW OF DEMO. The Problem of Energy Resources: Nuclear Fusion Power Plant, Power Supplies & Semiconductor Devices, Diodes & Thyristors, AC-DC Rectifiers, EU-DEMO Fusion Power Electrical System, Balance-Of-Plant (HCPB/WCLL); Major EU-DEMO subsystems (lessons learnt from ITER); EU DEMO Power Demand (SSEN–PPEN) 9. OPTIMIZATION AND INVERSE PROBLEMS IN MAGNETIC FUSION RESEARCH. Optimization Problems: Modelling, Optimization, Linear Programming, Linear Programming in Matlab, Quadratic Programming, Descent Methods, Exercises. Design of high flux expansion experiments in jet tokamak via optimization of the divertor coils current 10. SUPERCONDUCTORS: THEORY AND FUSION APPLICATION. The phenomenon of superconductivity: principles, phenomenology and materials. The main applications of superconductors. The technology of superconducting magnets for nuclear fusion: ITER and DTT. 11. THE ERA OF THE ATOM: ONE CENTURY AHEAD THE BOHR MODEL (seminar). 12. ADDITIONAL HEATING SCHEMES FOR TOKAMAKS. Scope of additional heatings, additional heating techniques, NBI, ICRH, ECRH, Task for HCD systems. 13. MECHANICAL AND ELECTROMAGNETIC FEM ANALYSIS OF TOKAMAKS COMPONENTS. Mechanical analysis of superconducting magnet systems: Central Solenoid (CS), Poloidal Field (PF) coils and Toroidal Field (TF) coils (FEM strategies: issues and applications (DEMO, DTT), Steady state and transient simulations. Liquid metals as PFC. Electromagnetic analysis of magnet system and metallic components (VV, in-vessel coils, etc.), Steady state and transient simulationsANSYS Workbench modules, Geometry (FE Modeler/SpaceClaim), Static structural, Contacts, cyclic symmetry, submodeling. Magnetostatic. ANSYS Maxwell, Geometry, Magnetostatics analysis, Transient analysis. Exercises and final project. 14. DYNAMIC MODEL OF BALANCE OF PLANT ON SIMULINK.
(reference books)
Lecture Notes and presentations Wesson, Tokamaks, Oxford University Press Pucella, Segre, Fisica dei plasmi, Zanichelli Ariola, Pironti, Magnetic Control and Tokamak Plasmas, Springer
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Dates of beginning and end of teaching activities
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From to |
Delivery mode
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Traditional
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Attendance
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not mandatory
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Evaluation methods
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Written test
Oral exam
A project evaluation
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|
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Module: NUCLEAR FUSION - module 2
(objectives)
The course will provide the basics necessary to physical (module II) and engineering (module I) understanding of fusion nuclear energy systems covering topics from magnetic confinement and plasma physics to plasma surface interaction, reactor materials, control systems and mechanics. The main objectives are (a) knowledge and key aspects of engineering, technology and physics associated with the ' magnetic fusion energy, (b) identification of the main features nuclear fusion tokamak devices , (c) knowledge of the state of the international research (JET, EAST, ASDEX) and perspectives of fusion nuclear energy (next experimental machines as DTT, ITER and DEMO). The expected learning results are: (i) the knowledge of the theoretical contents of the course (Dublin descriptor n°1), (ii) the competence in presenting technical argumentation skills (Dublin descriptor n°2), (iii) autonomy of judgment (Dublin descriptor n°3) in proposing the most appropriate approach to argue the request and (iv) the students' ability to express the answers to the questions proposed by the Commission with language properties, to support a dialectical relationship during discussion and to demonstrate logical-deductive and summary abilities in the exposition (Dublin descriptor n°4).
|
Language
|
ENG |
Type of certificate
|
Profit certificate
|
Credits
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4
|
Scientific Disciplinary Sector Code
|
ING-IND/31
|
Contact Hours
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32
|
Type of Activity
|
Related or supplementary learning activities
|
Teacher
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MINUCCI Simone
(syllabus)
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. TOKAMAK LOAD ASSEMBLY: FROM CONCEPTUAL DESIGN TO REALIZATION. Introduction. Toroidal Field Coil System. Poloidal Field Coil System. Vacuum Vessel. Divertor and First Wall. Cooling. Assembly maintenance (remote handling). Supply System. 5. NEUTRONIC. Basic neutron physics and breeding concept, introduction to neutron transport, neutronics and activation calculations. Introduction to neutron sources and material damage. 6. 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. 7. 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. 8. OVERVIEW ON TODAY POWER SUPPLY SYSTEMS FOR TOKAMAKS IN VIEW OF DEMO. The Problem of Energy Resources: Nuclear Fusion Power Plant, Power Supplies & Semiconductor Devices, Diodes & Thyristors, AC-DC Rectifiers, EU-DEMO Fusion Power Electrical System, Balance-Of-Plant (HCPB/WCLL); Major EU-DEMO subsystems (lessons learnt from ITER); EU DEMO Power Demand (SSEN–PPEN) 9. OPTIMIZATION AND INVERSE PROBLEMS IN MAGNETIC FUSION RESEARCH. Optimization Problems: Modelling, Optimization, Linear Programming, Linear Programming in Matlab, Quadratic Programming, Descent Methods, Exercises. Design of high flux expansion experiments in jet tokamak via optimization of the divertor coils current 10. SUPERCONDUCTORS: THEORY AND FUSION APPLICATION. The phenomenon of superconductivity: principles, phenomenology and materials. The main applications of superconductors. The technology of superconducting magnets for nuclear fusion: ITER and DTT. 11. THE ERA OF THE ATOM: ONE CENTURY AHEAD THE BOHR MODEL (seminar). 12. ADDITIONAL HEATING SCHEMES FOR TOKAMAKS. Scope of additional heatings, additional heating techniques, NBI, ICRH, ECRH, Task for HCD systems. 13. MECHANICAL AND ELECTROMAGNETIC FEM ANALYSIS OF TOKAMAKS COMPONENTS. Mechanical analysis of superconducting magnet systems: Central Solenoid (CS), Poloidal Field (PF) coils and Toroidal Field (TF) coils (FEM strategies: issues and applications (DEMO, DTT), Steady state and transient simulations. Liquid metals as PFC. Electromagnetic analysis of magnet system and metallic components (VV, in-vessel coils, etc.), Steady state and transient simulations. ANSYS Workbench modules, Geometry (FE Modeler/SpaceClaim), Static structural, Contacts, cyclic symmetry, submodeling. Magnetostatic. ANSYS Maxwell, Geometry, Magnetostatics analysis, Transient analysis. Exercises and final project. 14. DYNAMIC MODEL OF BALANCE OF PLANT ON SIMULINK.
(reference books)
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
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Dates of beginning and end of teaching activities
|
From to |
Delivery mode
|
Traditional
|
Attendance
|
not mandatory
|
Evaluation methods
|
Written test
Oral exam
A project evaluation
|
|
|
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