Published June 2004 | Version v1
Journal article

Helium retention of 316L stainless steel used for the first wall of the large helical device (LHD)

  • 1. Hokkaido Univ., Dept. of Nuclear Engineering, Sapporo, Hokkaido (Japan)

Description

Helium retention of 316L stainless steel used for LHD plasma facing material was evaluated after helium ion irradiation by using a technique of thermal desorption spectroscopy (TDS). After the irradiation with helium energy of a few hundreds eV, most of the retained helium desorbed in the temperature range lower than 550degC. With increase of ion energy, the ratio of helium desorbed in higher temperature range (> 550degC) increased. In the irradiation with a helium energy of 3 keV, the retained helium desorbed only in the higher temperature range. Based upon the obtained results, the desorption behavior of helium in the stainless steel sample exposed to the LHD plasma discharges was discussed. (author)

Additional details

Publishing Information

Journal Title
Shinku
Journal Volume
47
Journal Issue
6
Journal Page Range
p. 484-487
ISSN
0559-8516

Optional Information

Notes
8 refs., 4 figs.