[2L01-04] Plasma-material Interaction in Fusion Reactors

[2L02] Distribution of hydrogen isotopes retention in pre-damaged tungsten tile exposed to deuterium and helium mixed divertor plasma in LHD

*Mingzhong Zhao¹, Miyuki Yajima¹, Yasunori Hayashi², Kiyohiro Yabuuchi², Masayuki Tokitani¹, Gen Motojima¹, Suguru Masuzaki¹ (1. National Institute for Fusion Science, 2. Kyoto University)

Keywords:Tungsten, irradiation defects, LHD divertor plasma

This work aims to study the distribution pattern of hydrogen isotope retention on pre-damaged Tungsten (W) around strike of LHD as well as the Helium (He) effect. ITER grade tungsten (W) tiles, 28mm in length, 6mm in width and 1mm in thickness, were irradiated by 6.4MeV iron ion at Dual-Beam Facility for Energy Science and Technology. The peak damage level in W is 1 dpa. The undamaged and damaged W tiles will be exposure to the Deuterium (D) or D/He mixture plasma at the LHD divertor strike line position in 23rd campaign. After that, the tritium retention pattern, impurities deposition, surface morphology on W tiles will be studied by imaging plate and scanning electron microscope.