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Chapter 3

ITER – International

Thermonuclear Experimental

Reactor

Vitalij P. Muratov, Georgij L. Saksagansky, Oleg G. Filatov
JSC D.V. Efremov Scientific Research Institute of Electrophysical Apparatus, Saint
Petersburg, Russia

Chapter Outline
3.1 Introduction 39 3.5 In-vessel Components 54
3.2 ITER Reactor Configuration 3.5.1 First-Wall Panels 54
and Main Characteristics 42 3.5.2 Divertor 55
3.3 Magnet System 45 3.6 Thermal Shields 56
3.3.1 Toroidal Field Coils 47 3.7 Cryostat 57
3.3.2 Poloidal Field Coils 49 3.8 Reactor Assembly 60
3.3.3 Central Solenoid and Appendix A.3.1 Quality Assurance
Correction Coils 50 Programme for Reactor Design 60
3.4 Vacuum Vessel 52 References 66

3.1 INTRODUCTION
The construction of the International Thermonuclear Experimental Reactor
(ITER) heralds the completion of the initial stage of harnessing fusion energy.
The next strategic leap is to create a 1 GW demonstration reactor. Its launch is
scheduled for the second half of this century. The DEMO reactor, in turn, will
pave the way for commercial-scale fusion power plants [1].
In 1978, the academician E.P. Velikhov initiated a proposal (subsequently
articulated formally by the then Soviet government) to the international com-
munity to make an international tokamak experiment. Harnessing fusion energy
was intended to help humankind avoid a fatal energy shortage. In a later run, a
harmonised range of renewable energy resources, close-cycle fission reactors
and fusion reactors could promise the inhabitants of the Earth an unlimited sup-
ply of ‘clean energy.’ Other nations such as the United States, Japan and those in
the European Union (EU) gave a positive response, and an international fusion

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