Abstract
Preliminary experiment to evaluate, analyze, and reduce the gas accumulation of materials used in LHD as plasma facing components has been carried out using a test devices ACT and a thermal desorption spectrometer. As the test materials, stainless steel (SUS316L) and iso-graphite (IG-430U) are selected and installed inside the vacuum vessel of ACT as linings, which are near the same kinds as the first wall material and armor tile material of the divertor plate used in LHD, respectively. Each material is exposed to alternating glow discharge plasma with He and H2 gasses. Qualitative measurement using a quadruple mass filter indicates that the He gas amount released from the stainless steel wall during H2 glow discharge cleaning is several times as much as that released from the graphite wall, which is an unexpected result. This result does not contradict that of the thermal desorption spectrometer measurement for small samples exposed to He glow discharge plasma for 7 h.
Original language | English |
---|---|
Pages (from-to) | 239-244 |
Number of pages | 6 |
Journal | Journal of Nuclear Materials |
Volume | 313-316 |
Issue number | SUPPL. |
DOIs | |
Publication status | Published - Mar 1 2003 |
Event | Plasma - Surface Interactions in Controlled Fusion Devices - Gifu, Japan Duration: May 26 2002 → May 31 2002 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering