Fundamentals of magnetic fusion technology / International Atomic Energy Agency.

Format:

Book

Author/Creator:

International Atomic Energy Agency, author.

Series:

Non-Serial Publication

Language:

English

Subjects (All):

Fusion reactors.

Physical Description:

1 online resource (778 pages)

Edition:

First edition.

Place of Publication:

Vienna, Austria : International Atomic Energy Agency, [2023]

Summary:

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Contents:

Intro

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EDITORIAL NOTE

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CHAPTER 1

INTRODUCTION TO MAGNETIC FUSION AND FUSION REACTORS

1.2. Characteristics of magnetic fusion reactors

1.2.1. Fuel

1.2.2. Safety and the environment

1.2.2.1. Hazards in a fusion plant

(a) Tritium

(b) Neutron activation

(c) Activated corrosion products

(d) Erosion dust

(e) Radioactive inventory

(f) Non-nuclear hazards

1.2.2.2. Safety aspects of fusion

1.2.2.3. Environmental aspects of fusion

(a) Tritiated waste management

(b) Detritiation techniques

(c) Neutron activated waste management

1.2.3. Economic aspects

1.2.3.1. Economic viability of future fusion plants

1.2.3.2. The cost of fusion research

1.3. A tokamak fusion reactor

1.3.1. ITER and FPPs

1.3.1.1. The principal physics goals of ITER

1.3.1.2. The specific technological goals of ITER

1.3.2. Physics of a fusion reactor

1.3.2.1. Plasma confinement

1.3.2.2. Beta value

1.3.2.3. Density limit

1.3.2.4. Power exhaust

1.3.2.5. Current drive

1.3.2.6. Plasma diagnostics

1.3.2.7. Fusion neutronics

1.3.2.8. Plasma control

1.3.3. Engineering design of a fusion reactor

1.3.3.1. Magnets

1.3.3.2. Plasma facing components

1.3.3.3. Materials

1.3.3.4. Vacuum pumping and fuelling

1.3.3.5. Remote handling and maintenance

1.3.4. Stellarator based fusion reactors

1.3.5. From ITER to commercial FPPs

REFERENCES

CHAPTER 2

PLASMA HEATING AND CURRENT DRIVE TECHNOLOGY

Chapter 1

Chapter 2

2.1. INTRODUCTION

2.2. GENERAL PRINCIPLES

2.3. NEUTRAL BEAM INJECTION

2.2.

2.1.

2.3.1. General concept

2.3.2. Generation of fast neutral particles.

2.3.3. Generation of fast neutral particles

2.3.4. Transport of those particles inside a duct

2.3.5. Injection into the plasma

2.3.6. Propagation as neutral particles inside the plasma

2.3.7. Ionization and thermalization inside the plasma

2.4. GENERATION OF FAST NEUTRAL PARTICLES

2.4.1. Generation of ions

2.4.2. Extraction and acceleration of the ions

2.4.3. Neutralization of the accelerated ions

2.5. TRANSPORT OUTSIDE THE PLASMA

2.6. COUPLING

2.7. TRANSPORT INSIDE THE PLASMA

2.7.1. Absorption

2.7.2. Discussion of strength and weaknesses

2.7.3. Overview of parameters achieved and planned

2.7.4. Other uses

2.8. ION CYCLOTRON RANGE OF FREQUENCIES

2.8.1. General principles and waves in plasma

2.8.2. RF generator

2.8.3. Transport outside the plasma: transmission lines

2.8.4. Coupling

2.8.5. Transport inside the plasma

2.8.6. Absorption

2.8.7. Discussion of strength and weaknesses

2.8.8. Overview of parameters achieved

2.8.9. Other uses

2.9. LOWER HYBRID

2.9.1. Introduction

2.9.2. Klystrons

2.9.3. LH transmission lines: waveguides

2.9.4. Rectangular waveguides

2.9.4.1. Waveguide plumbery - a practical example

2.9.5. LHCD launchers

2.9.5.1. LH launcher main figures of merit

2.9.5.2. Grill launchers

2.9.5.3. Multijunction launchers

2.9.5.4. Passive-active waveguide array launchers

2.9.5.5. Poloidal splitter launchers

2.9.6. Wave propagation in the plasma

2.9.7. Wave absorption, Landau damping

2.9.8. Overall discussion of strength and weaknesses

2.9.9. Overview of parameters achieved and example of some systems

2.10. ELECTRON CYCLOTRON RESONANCE FREQUENCY

2.10.1. General principle

2.10.2. Gyrotron

2.3.

2.4.

2.5.

2.6.

2.7.

2.7.1.

2.7.2.

2.10.3. Transport outside

2.10.4. Coupling.

2.10.5. Transport inside the plasma

2.10.6. Absorption

2.10.7. Overall discussion of strength and weaknesses

2.10.8. Overview of parameters achieved and some examples of systems

2.10.9. Other uses

Chapter 3

3.1. INTRODUCTION

3.2. MAGNETIC DIAGNOSTICS

3.2.1. Passive coils and loops

3.2.2. Other passive methods to measure magnetic fields

3.2.3. Active MHD spectroscopy

3.3. MICROWAVE AND FAR INFRARED DIAGNOSTICS

3.3.1. Introduction

3.3.2. ECE

3.2.2.1. Fourier transform spectrometer or Michelson interferometer

3.2.2.2. Grating polychromator

3.2.2.3. Heterodyne radiometer

3.2.2.4. ECE imaging

3.2.2.5. ECA

3.3.3. Interferometry and polarimetry

3.3.3.1. Interferometry

3.3.3.2. Polarimetry

3.3.4. Reflectometry

3.3.4.1. Profile measurements

3.3.4.2. Fluctuation measurements

3.3.4.3. Doppler reflectometry

3.3.5. Microwave scattering

3.3.5.1. Collective scattering on plasma fluctuations

3.3.5.2. Ion collective Thomson scattering

3.4. SPECTROSCOPY

3.4.1. Visible and UV spectroscopy

3.4.1.1. Passive spectroscopy

3.4.1.2. Beam aided spectroscopy

3.4.1.3. Laser aided spectroscopy

3.4.2. XUV and VUV spectroscopy

3.4.3. SXR spectroscopy

3.4.3.1. Pulse height analysis

3.4.3.2. SXR arrays and tomography

3.4.3.3. X ray crystal spectroscopy

3.5. BOLOMETRY

3.6. PARTICLE DIAGNOSTICS

3.6.1. NPA

3.6.2. Active beam scattering

3.6.2.

3.6.3. Heavy ion beam probe

3.7. FUSION PRODUCT DIAGNOSTICS

3.7.1. Neutron diagnostics

3.7.1.1. Neutron counters

3.7.1.2. Activation systems

3.7.1.3. Neutron cameras (neutron profile monitors)

3.7.1.4. Neutron spectroscopy

3.7.2. Gamma ray diagnostics

3.7.3. Fast ion loss measurements

3.7.4. Confined fast ion measurements.

3.8. FIRST WALL AND OPERATIONAL DIAGNOSTICS

3.8.1. Infrared, visible and UV measurements of the plasma edge

3.8.1.1. Infrared cameras

3.8.1.2. Visible and UV cameras

3.8.2. Pressure and gas analysis measurements

3.8.2.1. Ionization gauges

3.8.2.2. Residual gas analysis

3.8.3. Probes

3.8.4. Erosion and deposition measurements

3.8.5. Dust measurements

3.9. ISSUES OF IMPORTANCE FOR REACTORS

3.9.1. Applying diagnostics to fusion reactors

3.10. DATA HANDLING

3.11. ACKNOWLEDGEMENT

CHAPTER 5 MAGNETIC CONFINEMENT

5.1. INTRODUCTION

5.2. Superconducting magnets for magnetic confinement fusion

5.2.1. From JET to Tore Supra and ITER

5.2.2. The ITER adventure

5.2.2.1. An engineering approach to ITER dimensioning

5.2.2.2. The superconducting magnet system for ITER

5.2.3. The ITER TF system: double pancakes inserted within steel plates

5.2.4. Validation of the magnet system design: the ITER model coils

Chapter 5

5.1.

5.2.

5.2.1.

5.2.2.

5.2.3.

5.2.4.

5.2.5. DEMO: the next step on from ITER

1

2

3

4

4.1

4.2

5.3. INTRODUCTION TO APPLIED SUPERCONDUCTIVITY

5.3.1. Superconductivity

5.3.2. Critical field and critical temperature

5.3.3. Applications of superconductivity: the NbTi era

5.3.4. Superconducting strands

5.3.5. Critical current density

5.3.5.1. The I-V curve

5.3.5.2. I-V testing of a strand sample

5.3.5.3. I-V testing of an ITER conductor sample: the SULTAN test facility

5.3.6. Parameterization of critical current density

5.3.6.1. Parameterization of niobium-titanium

5.3.6.2. Parameterization of Nb3Sn

5.3.7. Temperature margin, current sharing temperature and load line

5.3.7.1. Current sharing temperature Tcs

5.3.7.2. Load line and temperature margin

5.3.8. Superconducting materials in ITER.

5.4. The cable in conduit concept for conductors

5.4.1. Fusion magnets: fast energy deposition and CICC temperature margin

5.4.2. Cryogenic loss removal by forced flow of helium

5.4.2.1. Illustration of the ITER TF cable

5.4.3. Pump work

5.4.3.1. Illustration: estimation of the pump work of the ITER TF system

5.4.4. CICC design

5.4.4.1. Illustration: application to the ITER TF system

5.5. Quench protection in fusion magnets

5.5.1. High voltages

5.5.2. The hotspot criterion

5.5.3. The quench protection circuit

5.5.3.1. Maximum voltage across the coil during FSDs

5.5.3.2. Impact of Vb,max on current breakers (or switches), the acquisition system and the insulation

5.5.3.3. Voltage reduction by coil subdivision

5.5.3.4. Illustration: application to JT-60SA

5.5.3.5. Illustration: application to Tore Supra

5.5.3.6. Voltage reduction by variable resistance

5.5.3.7. Components of the QPCs

(a) Current breakers

(b) Discharge resistors

5.5.4. Quench detection in fusion magnets

5.5.4.1. Selection of quench detection parameters

5.5.4.2. Compensation of the inductive part of the voltage

(a) The classical bridge circuit

(b) Other methods to balance the inductive voltage

5.5.4.3. The co-wound tape

5.6. Conclusion

Chapter 4

Chapter 6

PLASMA FACING COMPONENTS

6.1. INTRODUCTION

6.2. THE IN-VESSEL CORE CONFIGURATION

6.3. PLASMA IN-VESSEL COMPONENT INTERACTION

6.1.

6.2.

6.3.

6.3.1. Plasma-edge interactions with the first wall

6.3.2. Neutron interaction

6.3.3. Cyclic and high temperature loads

6.3.4. Dust formation.

6.3.5. Component damage and replacement.

Notes:

Description based on publisher supplied metadata and other sources.

Part of the metadata in this record was created by AI, based on the text of the resource.

Description based on print version record.

Includes bibliographical references.

Other Format:

Print version: IAEA Fundamentals of Magnetic Fusion Technology

ISBN:

9789201104212

9201104219

OCLC:

1412620489