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Fundamentals of magnetic thermonuclear reactor design / edited by Vasilij Glukhikh, Oleg Filatov, Boris Kolbasov.
- Format:
- Book
- Series:
- Woodhead Publishing in energy.
- Woodhead Publishing Series in Energy
- Language:
- English
- Subjects (All):
- Nuclear reactors--Design and construction.
- Nuclear reactors.
- Physical Description:
- 1 online resource (476 pages).
- Edition:
- 1st ed.
- Place of Publication:
- Duxford, England : Woodhead Publishing, [2018]
- Summary:
- 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.
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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
- 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.
- Notes:
- Includes index.
- Description based on print version record.
- Description based on publisher supplied metadata and other sources.
- ISBN:
- 9780081024713
- 0081024711
- 9780081024706
- 0081024703
- OCLC:
- 1038487126
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