Studies of the fast ion confinement in the Large Helical Device by using neutron measurement and integrated codes

The neutral beam (NB) fast ion confinement in the Large Helical Device (LHD) is studied for several full field ($B_t∼ 2.75~T$) magnetic configurations by a combination of neutron measurement and simulations. To investigate the NB fast ion confinement, we have performed a series of short-pulse NB injection experiments. The experiment results are analysed by the integrated code TASK3D-a. From this investigation, the effective particle diffusion coefficients of the tangential and perpendicular NBs are approximately $D^{eff}∼ 0.1~m²~s^{-1}$ and $D^{eff}∼ 1~m²~s^{-1}$ in the standard configuration. It is clarified that the NB fast ion confinement improves when the plasmas are shifted inward. Moreover, it is also found that the simulation, which considers the deuteron dilution effect due to the presence of impurity ions, can describe a neutron emission rate consistent with the measurement.