Plasma and Fusion Research
Volume 9, 3405135 (2014)
Regular Articles
- Hydrogen Iosotope Research Center, University of Toyama, 3190 Gofuku, Toyama 930-8555, Japan
- 1)
- National Institute for Fusion Science, Toki 509-5292, Japan
- 2)
- Radiochemistry Research Laboratory, Shizuoka University, Shizuoka 422-8529, Japan
- 3)
- Laboratory of Plasma Physics and Engineering, Hokkaido University, Sapporo 060-8628, Japan
Abstract
Effects of pre-heating for retention and distribution of tritium have been studied using samples fixed on the wall of the Large Helical Device during a plasma campaign. The samples were fixed at four different locations. The plasma-facing surface of the samples was covered with deposition layers of different thickness in each sample. Retention behavior in deposition layers was observed using β-ray-induced X-ray spectrometry and imaging plate technique. Pre-heating of the samples in vacuum was changed in a temperature range from 300 to 623 K, and subsequent tritium exposure was carried out at 300 K in every runs. Non-uniformity of tritium distribution clearly appeared even in the as-received samples which was not pre-heated. It is considered, therefore, that non-uniform adsorption sites of tritium have been produced during a formation process of deposition layers. In addition, it was seen that the amount of tritium retention increased with an increase in the pre-heating temperature, indicating that adsorption sites of tritium were newly formed in the deposition layers by heating in vacuum.
Keywords
tritium retention, plasma-facing material, deposition layer, β-ray-induced X-ray spectrometry
Full Text
References
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This paper may be cited as follows:
Masao MATSUYAMA, Shinsuke ABE, Kiyohiko NISHIMURA, Naoko ASHIKAWA, Yasuhisa OYA, Kenji OKUNO, Yuji YAMAUCHI, Yuji NOBUTA and Akio SAGARA, Plasma Fusion Res. 9, 3405135 (2014).