[2L01-04] 核融合炉プラズマ材料相互作用

[2L02] LHDダイバータプラズマに曝されたタングステンタイル中の水素同位体蓄積の分布

*趙 明忠¹、矢嶋 美幸¹、林 慶知²、薮内 聖皓²、時谷 政行¹、本島 厳¹、増崎 貴¹ (1. 核融合科学研究所、2. 京都大学)

キーワード：タングステン、照射欠陥、LHDダイバータプラズマ

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.