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Chapter 11
Power Supply Systems
Alexandr G. Roshal
JSC D.V. Efremov Scientific Research Institute of Electrophysical Apparatus,
Saint Petersburg, Russia
Chapter Outline
11.1 Introduction 323 11.3.2 Plasma Equilibrium
11.2 Power Supply for Toroidal Control Coils 336
Field Coils 324 11.3.3 ITER Poloidal Field Coil
11.2.1 Resistive Coils 324 Power Supply 337
11.2.2 Superconducting Coils 327 11.4 Switching Equipment 343
11.2.3 ITER Toroidal Field 11.4.1 Switching Equipment for
Coil Power Supply 330 Experimental Facilities 343
11.3 Poloidal Field Coil Power 11.4.2 ITER Switching
Supply 333 Equipment 344
11.3.1 Central Solenoid Coils 333 References 348
11.1 INTRODUCTION
The development of tokamaks is in close connection with the quest for larger
plasma volume and longer discharge and, hence, more powerful magnetic sys-
tems. The more work a magnet does the more electric energy it consumes. A
power supply (PS) system has to meet stringent requirements. This is essential
for ensuring that the magnetic field has the required strength and shape and that
it changes according to the right law during the operating cycle.
In a large fusion machine, the pulsed power of the PS system reaches
2.5 GW, and energy stored in the magnetic field is up to 3 GJ. The ITER is de-
signed to have an even more impressive PS system, with a total stored magnetic
energy more than 60 GJ, and the pulsed power developed during emergency
discharge of energy from superconducting coils in case of superconductor-to-
normal transition (quench) amounting to 9 GW.
Since the early days of tokamak research, the PS systems have developed
from unsophisticated, capacitor-bank-based devices to unique electrical engi-
neering systems. Today, the PS systems for fusion applications are based on
the latest electric power system research developments and actually represent
a separate area of pulse engineering. This is due not only to the scale of these
Fundamentals of Magnetic Thermonuclear Reactor Design. http://dx.doi.org/10.1016/B978-0-08-102470-6.00011-1
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