ELECTRICAL ENGINEERING PROBLEMS OF THE TOKAMAK FUSION TEST REACTOR.

G. Karady, C. Neumeyer, R. Cassel, J. Murray

Research output: Contribution to journalConference article

Abstract

The Tokamak Fusion Test Reactor has several large coils designated for plasma initiation, confinement, heating, and position control. The coils are supplied by high current pulses with an approximate duration of 10 sec and a repetition period of 5 minutes. The peak power of the pulses is approximately 900 MW with an average power of 30 MW. This paper describes the engineering problems related to the experimental reactor and discusses the flywheel generator energy storage system, the developed rectifier/inverter arrangement, and an operational method which minimizes the reactive power consumption and insures the safe dissipation of magnetic energy in case of a fault. In addition, the switching problem related to the required swing of large current in the ohmic heating coils is analyzed.

Original languageEnglish (US)
JournalAmerican Society of Mechanical Engineers (Paper)
StatePublished - Jan 1 2017
EventIEEE/ASME/ASCE Jt Power Gener Conf, Pap - Charlotte, NC, USA
Duration: Oct 7 1979Oct 11 1979

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Plasma confinement
Experimental reactors
Flywheels
Joule heating
Electrical engineering
Position control
Reactive power
Energy storage
Electric power utilization
Fusion reactions
Plasmas
Heating

ASJC Scopus subject areas

  • Mechanical Engineering

Cite this

ELECTRICAL ENGINEERING PROBLEMS OF THE TOKAMAK FUSION TEST REACTOR. / Karady, G.; Neumeyer, C.; Cassel, R.; Murray, J.

In: American Society of Mechanical Engineers (Paper), 01.01.2017.

Research output: Contribution to journalConference article

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