Annual Report 35 - 1 Original
Surface Properties and Retention of Helium in Stainless Steel Exposed to LHD Plasmas
N. Yoshida1, N. Yugami2, Y. Kimura2, T. Fujiwara1, K. Araki1, R. Yoshihara1,
H. Watanabe1,
M. Tokitani3, S. Masuzaki3, Y. Hatano4, M. Matsuyama4, Y. Oya5, K. Okuno5
1Research Institute for Applied Mechanics, Kyushu University, Kasuga-Koen, Kasuga, Fukuoka 816-8580, Japan
2Interdisciplinary Graduate School of Engineering Sciences, Kyushu University, Kasuga-Koen, Kasuga, Fukuoka 816-8580, Japan
3National Institute for Fusion Science, Oroshi, Toki, Gifu 509-5292, Japan
4 Hydrogen Isotope Research Center, Organization for Promotion or Research, University of Toyama, Gofuku, Toyama 930-8555, Japan
5Faculty of Science, Shizuoka University, Ohya, Suruga-ku, Shizuoka 422-8529, Japan
Abstract
Modification of the plasma facing surface of LHD and its effects on the retention and desorption of He were examined by exposing 316L stainless steel coupons to LHD plasmas.
In the erosion dominant area, formation of dense He bubbles and mixing of deposited impurities (C, O, Fe, Cr, Ni) occurred in a subsurface region of about 20 nm-thick. In the deposition dominant area, the surface was covered by a porous carbon rich layer. Retention of He was saturated in both areas. In the erosion dominant area, He was trapped by the radiation-induced defects formed in the very thin subsurface region.
The concentration of He trapped in the impurity deposition (He/C) in the deposition dominant area was estimated to be 0.9%.