Tritium retention on the surface of stainless steel samples fixed on the plasma-facingwall in LHD

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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 300K 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.

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Matsuyama, M., Abe, S., Nishimura, K., Ashikawa, N., Oya, Y., Okuno, K., … Sagara, A. (2014). Tritium retention on the surface of stainless steel samples fixed on the plasma-facingwall in LHD. Plasma and Fusion Research, 9(SpecialIssue2). https://doi.org/10.1585/pfr.9.3405135

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