Fundamentals of magnetic thermonuclear reactor design
'Fundamentals of Magnetic Thermonuclear Reactor Design' is a comprehensive resource on fusion technology and energy systems written by renowned scientists and engineers from the Russian nuclear industry. It brings together a wealth of invaluable experience and knowledge on controlled therm...
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| Other Authors | , , |
|---|---|
| Format | Electronic eBook |
| Language | English |
| Published |
Duxford, United Kingdom :
Woodhead Publishing, an imprint of Elsevier,
2018.
|
| Series | Woodhead Publishing in energy.
|
| Subjects | |
| Online Access | Full text |
| ISBN | 9780081024713 0081024711 9780081024706 0081024703 |
| Physical Description | 1 online resource |
Cover
Table of Contents:
- Cover
- Title Page
- Copyright Page
- Book Summary
- Contents
- List of Contributors
- Preface
- Acknowledgements
- Disclaimer
- Abbreviations
- Designations
- Chapter 1
- Engineering and Physical Principles of the Magnetic Fusion Reactor Operation
- 1.1
- Introduction
- 1.2
- Physical Basis of Fusion Power Engineering
- 1.3
- Basic Correlations
- References
- Chapter 2
- Facilities With Magnetic Plasma Confinement
- 2.1
- Introduction
- 2.2
- Overview
- 2.2.1
- Tokamaks
- 2.2.2
- Stellarators
- 2.2.3
- Magnetic Mirrors
- 2.2.4
- Hybrid Systems
- 2.2.5
- Pinches
- 2.2.6
- Spheromaks
- 2.3
- Structure and Typical Parameters of Tokamak Reactors
- 2.4
- Physical and Engineering Limitations for Parameter Selection
- 2.5
- Engineering Requirements to Main Functional Systems
- 2.5.1
- Magnet System
- 2.5.2
- In-Chamber Conditions: Breakdown
- 2.5.3
- Force Loads on Tokamak Components
- 2.5.4
- Fuel Cycle: Demand for Tritium
- 2.5.5
- Radiation Shielding
- 2.6
- Stellarators
- 2.6.1
- Functional Layout and Key Characteristics
- 2.6.2
- Research Facilities
- 2.6.3
- Stellarator Fusion Reactor
- References
- Chapter 3
- ITER
- International Thermonuclear Experimental Reactor
- 3.1
- Introduction
- 3.2
- ITER Reactor Configuration and Main Characteristics
- 3.3
- Magnet System
- 3.3.1
- Toroidal Field Coils
- 3.3.2
- Poloidal Field Coils
- 3.3.3
- Central Solenoid and Correction Coils
- 3.4
- Vacuum Vessel
- 3.5
- In-vessel Components
- 3.5.1
- First-Wall Panels
- 3.5.2
- Divertor
- 3.6
- Thermal Shields
- 3.7
- Cryostat
- 3.8
- Reactor Assembly
- Appendix A.3.1 Quality Assurance Programme for Reactor Design
- References
- Chapter 4
- Simulation of Electromagnetic Fields
- 4.1
- Introduction
- 4.2
- Stationary and Quasi-stationary Fields
- 4.3
- Stationary Field Analysis and Synthesis.
- 4.3.1
- Stationary Field Analysis
- 4.3.2
- Stationary Field Synthesis
- 4.3.3
- Ripple of the Tokamak Toroidal Field
- 4.4
- Analysis of Electromagnetic Transients
- 4.4.1
- Calculation and Methodological Basics
- 4.4.2
- Sources of Transient Fields
- 4.4.3
- Global Computational Models Based on Conducting Shells
- 4.4.4
- 3D Computational Models
- 4.4.5
- Computation of Potentials: Global and Local Model Integration
- Appendix A.4.1 Example of How to Synthesise a Ferromagnetic Insert
- Appendix A.4.2 Examples of FE Meshing of Conducting Shell Models for ITER Components
- Appendix A.4.3 Examples of 3D FE Meshes for Massive Conducting Structures of ITER
- References
- Chapter 5
- Superconducting Magnet Systems
- 5.1
- Introduction
- 5.2
- Superconducting Magnet Systems of Electrophysical Facilities
- 5.2.1
- Summary Characteristics of Superconducting Magnets
- 5.2.2
- ITER Magnets
- 5.3
- Physical and Mechanical Properties of Superconductors
- 5.3.1
- Flux Pinning
- 5.3.2
- Critical Characteristics
- 5.3.3
- Intrinsic Stabilisation
- 5.4
- Winding Superconductors
- 5.4.1
- Normal Phase Effect
- 5.4.2
- Forced-Flow Cooled Superconducting Cables
- 5.4.3
- Basic Superconducting Strands
- 5.4.4
- Superconducting Coil Cable Manufacturing Processes
- 5.5
- Modelling of the ITER Magnet System
- 5.5.1
- International Model Coil Program
- 5.5.2
- Toroidal Field Model Coil
- 5.5.3
- Model Insert Coils
- 5.5.4
- Main Simulation and Testing Results
- Appendix A.5.1 Thermal-Hydraulic Simulations of ITER Superconducting Magnets at Normal and Off-Normal Operation
- A.5.1.1 Venecia Basic Models and Modelling Technique
- A.5.1.2 Validation of Vincenta/Venecia Models for Thermal-Hydraulic Analysis of SC Magnets and Their Cryogenic Circuits
- A.5.1.2.1 Central Solenoid Model Coil
- A.5.1.2.2 Simulations Versus Experiments.
- A.5.1.3 Thermal-Hydraulic Models of ITER Magnets
- A.5.1.3.1 Toroidal Field Magnet Model
- A.5.1.3.2 Central Solenoid Model
- A.5.1.3.3 Model of PF Magnet System
- A.5.1.4 Mitigation of Pulsed Heat Loads
- References
- Chapter 6
- Vacuum and Tritium System
- 6.1
- Introduction
- 6.2
- Physical Processes in the Vacuum Chamber
- 6.3
- Plasma Impact on the First Wall
- 6.4
- Plasma Impurity Control
- 6.4.1
- Sources of Impurities
- 6.4.2
- Impurity Control Methods: The Magnetic Divertor
- 6.5
- Design Evaluation of Vacuum Parameters
- 6.6
- Vacuum Equipment and Processes
- 6.6.1
- Vacuum System Key Components
- 6.6.2
- Vacuum Boundary of Reactor
- 6.6.2.1
- Dual Functionality FW Design Concept
- 6.6.2.2
- Separate Functionality FW Design Concept
- 6.6.3
- Vacuum Pumping Duct Design
- 6.6.4
- Wall Cleaning and Conditioning
- 6.6.5
- Vacuum Pumping Equipment
- 6.7
- Mathematical Simulation of High-Vacuum Systems
- References
- Chapter 7
- First Wall Components
- 7.1
- Introduction
- 7.2
- First-Wall Design Principles
- 7.2.1
- Design Algorithm
- 7.2.2
- Initial Stage Design
- 7.2.3
- Estimation of the Engineering and Physical Characteristics of the First-Wall Components
- 7.2.3.1
- Heat Load Estimation
- 7.2.3.2
- Determination of Coolant's Parameters
- 7.2.3.3
- Material Selection
- 7.2.3.4
- Estimation of the First-Wall Thickness and Temperature Field
- 7.2.3.5
- Armour Erosion Lifetime
- 7.2.3.6
- Strength and Fatigue Lifetime
- 7.3
- ITER First Wall
- 7.3.1
- First-Wall Components
- 7.3.2
- Component Modelling: Technological and Testing Facilities
- 7.3.3
- Prevention of Destructive Events
- 7.4
- Next-Generation Reactor First Wall
- 7.4.1
- Challenges
- 7.4.2
- Possible Engineering and Physical Solutions
- 7.5
- Alternative Uses of First-Wall Technologies
- References
- Chapter 8
- Plasma Control System.
- 8.1
- Introduction
- 8.2
- Scope of the Control System Design Problem
- 8.3
- Basic Design Methodology
- 8.4
- Mathematical Modelling of Electromagnetic Processes
- 8.4.1
- Derivation of Linear Models
- 8.4.2
- Non-linear Modelling
- 8.5
- Analytical Synthesis and Control System Optimisation
- 8.5.1
- Basic Concept
- 8.5.2
- Problem Generalisation
- 8.6
- Plasma Start-Up Phase
- 8.6.1
- Dynamics of Tokamak Electromagnetic Processes
- 8.6.2
- Plasma Transport Model at Start-Up Phase
- 8.7
- Correction of Error Fields
- 8.7.1
- Effect of Error Fields on Plasma Processes
- 8.7.2
- Field Perturbation Harmonic Analysis
- 8.7.3
- ITER Correction Coils
- 8.8
- Plasma Column Position and Shape Reconstruction Based on Magnetic Measurements
- 8.8.1
- Basic Principles
- 8.8.2
- Reconstruction Methods
- References
- Chapter 9
- Plasma Heating Systems
- 9.1
- Introduction
- 9.2
- Ohmic Heating
- 9.3
- Additional Heating Methods
- 9.3.1
- Neutral Beam (NB) Injection
- 9.3.2
- Electron Cyclotron Resonance Heating
- 9.3.3
- Ion Cyclotron Resonance Heating
- 9.3.4
- Lower Hybrid Resonance Heating
- References
- Chapter 10
- Blanket
- 10.1
- Introduction
- 10.2
- Key Functions and Resulting Performance Requirements
- 10.3
- Blanket Design Algorithm
- 10.4
- Blanket Designs for Demonstration and Commercial Reactors
- 10.4.1
- Gen-1 Blankets
- 10.4.2
- Prospective Blanket Concepts
- 10.5
- ITER Test Blanket Modules
- 10.5.1
- Purpose and Objectives of the Test Modules
- 10.5.2
- Characteristics of Test Blanket Modules
- 10.6
- Blanket Design Problems
- References
- Chapter 11
- Power Supply Systems
- 11.1
- Introduction
- 11.2
- Power Supply for Toroidal Field Coils
- 11.2.1
- Resistive Coils
- 11.2.2
- Superconducting Coils
- 11.2.3
- ITER Toroidal Field Coil Power Supply
- 11.3
- Poloidal Field Coil Power Supply.
- 11.3.1
- Central Solenoid Coils
- 11.3.2
- Plasma Equilibrium Control Coils
- 11.3.3
- ITER Poloidal Field Coil Power Supply
- 11.4
- Switching Equipment
- 11.4.1
- Switching Equipment for Experimental Facilities
- 11.4.2
- ITER Switching Equipment
- References
- Chapter 12
- Mechanics of Magnetic Fusion Reactors
- 12.1
- Introduction
- 12.2
- Tokamak Superconducting Magnet: Load Schemes
- 12.2.1
- System of Toroidal Field Coils
- 12.2.2
- Poloidal Field Coils and Central Solenoid
- 12.2.3
- General Algorithm for Design and Computation
- 12.3
- Computations for Composite Windings
- 12.4
- Stress-Strain State of Tokamak Load-Bearing Structures
- 12.4.1
- Global and Local Computational Models
- 12.4.2
- Reaction to Off-Normal Current Combinations in Windings
- 12.4.3
- Accident Scenarios
- 12.4.4
- Thermal Mechanics of Superconducting Magnet Systems
- 12.5
- Magneto-Elastic Stability
- 12.5.1
- Problem Statement
- 12.5.2
- Stability of Toroidal and Poloidal Field Systems
- 12.6
- Strength and Stiffness Analysis of a Vacuum Vessel
- 12.6.1
- Mechanical Loads
- 12.6.2
- Strength and Life-Time
- 12.7
- Stellarator Structural Analysis
- Appendix A.12.1
- Magneto-elastic Stability of ITER Poloidal Field Coil System
- Appendix A.12.2
- Poloidal Field Coil Magneto-elastic Stability Under the Action of Tokamak Toroidal Field
- Appendix A.12.3
- Physical Simulation of ITER Toroidal Field Coil
- Appendix A.12.4
- Codes and Standards for Tokamaks
- References
- Chapter 13
- Structural and Functional Materials: Selection Criteria and Radiation Characteristics
- 13.1
- Introduction
- 13.2
- Selection Criteria
- 13.3
- Comparative Characteristics of Different Materials
- 13.4
- Plasma-Facing Materials
- 13.4.1
- Beryllium Alloys
- 13.5
- Heat-Conductive Materials
- 13.5.1
- High-Strength Copper Alloys.
- 13.5.2
- Radiation Characteristics of Copper Alloys.