For a detailed prediction of the plasma parameters in the Large Helical Device (LHD), 3-D equilibrium/1-D transport simulations including empirical or drift wave turbulence models are performed which suggest that the global confinement time of the LHD is determined mainly by the electron anomalous transport in the plasma edge region rather than by the helical ripple transport in the core region. Even if the ripple loss can be eliminated, the increase in global confinement is 10. However, the rise in the central ion temperature is more than 20. If the anomalous loss can be reduced to half of the value used in the present scaling, as is the case in the H-mode of tokamak discharges, the neoclassical ripple loss through the ion channel becomes important even in the plasma core. The 5 radial inward shift of the plasma column with respect to the major radius improves the plasma confinement and increases the fusion product by more than 50 by reducing the neoclassical asymmetric ion transport loss and increasing the plasma radius (10)
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