Correlation between the Plasma Parameters and the External Resonant Helical Fields in Tokamaks

Determinations of poloidal beta, plasma energy, plasma pressure, plasma temperature, plasma resistance, and plasma effective atomic number are important in tokamak plasma experiments. In this paper we describe a theoretical and experimental approach especially based on toroidal flux loop for measurement of these parameters in presence of Rotating Helical Field (RHF) in IR-T1 tokamak. For this purposes a diamagnetic loop with its compensation coil constructed and installed on outer surface of the IR-T1. Also in this work we measured the plasma current, plasma voltage, and the plasma density from the Rogowski coil, poloidal flux loop, and the Langmuir probe measurements, respectively. Experimental results show that the addition of a relatively small amount of RHF with L=2 and L=3 modes could be effective for improving the quality of tokamak plasma discharge by creating the steady state plasma.