[1J01-05] Fusion Reactor Component Technology (Divertor)

[1J05] Heat load analysis of the divertor tile of Large Helical Device during long pulse discharge

＊Hiroto Matsuura¹, Ippei Watanabe², Hirohiko Tanaka³, Yasuhiro Suzuki³, Kenichi Nagaoka³ (1.Radiation Research Center, Osaka Pref. Univ., 2.The Graduate University for Advanced Studies, 3.National Institute for Fusion Science)

Keywords:Large Helical Device, heat flux estimation, divertor tile, magnetic axis position swinging

In Large Helical Device, high temperature plasma is successfully confined for more than 30 minutes. In such experiment, in order to avoid discharge termination due to excess temperature increment of the divertor plate, the footpoint position of divertor plasma on the plate is moved periodically with magnetic axis position swinging. In this work, the unsteady heat flux analytic method developed for thermal probes is applied to thermocouple signal embeded in the divertor tiles and heat flux evolution onto tiles is estimated. Its results are also compared with Infarred camera data and magnetic field calculation.