Authors: A Salar Elahi M Ghoranneviss
Publish Date: 2009/06/30
Volume: 28, Issue: 4, Pages: 394-
Abstract
Plasma energy confinement time is one of the main parameters of tokamak plasma and Lawson criterion In this paper we present an experimental method especially based on diamagnetic loop toroidal flux loop for measurement of this parameter in presence of resonance helical field RHF in IRT1 tokamak For this purpose a diamagnetic loop with its compensation coil constructed and installed on outer surface of the IRT1 Also in this work we measured the plasma current and plasma voltage from the Rogowski coil and poloidal flux loop measurements Measurement results of plasma energy confinement time with and without RHF L = 2 L = 3 L = 2 3 show that the addition of a relatively small amount of RHF could be effective for improving the quality of tokamak plasma discharge by flatting the plasma current and increasing the energy confinement time
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