Plasma Transport Modeling for Tokamak and Helical Systems
K. Yamazaki, N. Nakajima, S. Murakami, M. Yokoyama
Abstract
K. Yamazaki, N. Nakajima, S. Murakami, M. Yokoyama
Abstract
The plasma transport code TOTAL (Toroidal Transport Analysis Linkage) is developed to clarify physics properties of both tokamak and helical plasmas. This is composed of one-dimensional transport code with magnetic ripple effects and three-dimensional equilibrium code with bootstrap currents. Ballooning-mode marginal-stable spherical tokamak configurations have been studied and their high beta values are found to be consistent with the normalized beta scaling. However, the engineering beta defined by maximum toroidal field on the plasma surface is found as small as the standard tokamak. The L:uge Helical Device (LHD) plasmas are also studied using this code, and the bootstrap cunent is found to make the radial axis-shift smaller, which leads to the decrease in the neoclassical ripple transport loss and the increase in the attainable plasma temperature.
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The plasma transport code TOTAL (Toroidal Transport Analysis Linkage) is developed to clarify physics properties of both tokamak and helical plasmas. This is composed of one-dimensional transport code with magnetic ripple effects and three-dimensional equilibrium code with bootstrap currents. Ballooning-mode marginal-stable spherical tokamak configurations have been studied and their high beta values are found to be consistent with the normalized beta scaling. However, the engineering beta defined by maximum toroidal field on the plasma surface is found as small as the standard tokamak. The L:uge Helical Device (LHD) plasmas are also studied using this code, and the bootstrap cunent is found to make the radial axis-shift smaller, which leads to the decrease in the neoclassical ripple transport loss and the increase in the attainable plasma temperature.
Key concepts: Tokamak, Plasma, Ripple, BETA (programming language), Toroid, Physics, Ballooning, Magnetic confinement fusion