Investigation of the trapped helium and hydrogen ions in plasma facing materials for LHD using thermal desorption spectrometer and alternating glow discharge cleanings

Y. Kubota; N. Noda; A. Sagara; H. Suzuki; S. Masuzaki; Kazutoshi Tokunaga; T. Satow; K. Yamazaki; O. Motojima

doi:10.1016/S0022-3115(02)01486-1

Investigation of the trapped helium and hydrogen ions in plasma facing materials for LHD using thermal desorption spectrometer and alternating glow discharge cleanings

Y. Kubota, N. Noda, A. Sagara, H. Suzuki, S. Masuzaki, Kazutoshi Tokunaga, T. Satow, K. Yamazaki, O. Motojima

Division of Nuclear Fusion Dynamics

Research output: Contribution to journal › Conference article › peer-review

9 Citations (Scopus)

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	https://doi.org/10.1016/S0022-3115(02)01486-1
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

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10.1016/S0022-3115(02)01486-1

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Kubota, Y., Noda, N., Sagara, A., Suzuki, H., Masuzaki, S., Tokunaga, K., Satow, T., Yamazaki, K., & Motojima, O. (2003). Investigation of the trapped helium and hydrogen ions in plasma facing materials for LHD using thermal desorption spectrometer and alternating glow discharge cleanings. Journal of Nuclear Materials, 313-316(SUPPL.), 239-244. https://doi.org/10.1016/S0022-3115(02)01486-1

Investigation of the trapped helium and hydrogen ions in plasma facing materials for LHD using thermal desorption spectrometer and alternating glow discharge cleanings. / Kubota, Y.; Noda, N.; Sagara, A.; Suzuki, H.; Masuzaki, S.; Tokunaga, Kazutoshi; Satow, T.; Yamazaki, K.; Motojima, O.

In: Journal of Nuclear Materials, Vol. 313-316, No. SUPPL., 01.03.2003, p. 239-244.

Research output: Contribution to journal › Conference article › peer-review

Kubota, Y, Noda, N, Sagara, A, Suzuki, H, Masuzaki, S, Tokunaga, K, Satow, T, Yamazaki, K & Motojima, O 2003, 'Investigation of the trapped helium and hydrogen ions in plasma facing materials for LHD using thermal desorption spectrometer and alternating glow discharge cleanings', Journal of Nuclear Materials, vol. 313-316, no. SUPPL., pp. 239-244. https://doi.org/10.1016/S0022-3115(02)01486-1

Kubota, Y. ; Noda, N. ; Sagara, A. ; Suzuki, H. ; Masuzaki, S. ; Tokunaga, Kazutoshi ; Satow, T. ; Yamazaki, K. ; Motojima, O. / Investigation of the trapped helium and hydrogen ions in plasma facing materials for LHD using thermal desorption spectrometer and alternating glow discharge cleanings. In: Journal of Nuclear Materials. 2003 ; Vol. 313-316, No. SUPPL. pp. 239-244.

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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.",

author = "Y. Kubota and N. Noda and A. Sagara and H. Suzuki and S. Masuzaki and Kazutoshi Tokunaga and T. Satow and K. Yamazaki and O. Motojima",

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AU - Kubota, Y.

AU - Noda, N.

AU - Sagara, A.

AU - Suzuki, H.

AU - Masuzaki, S.

AU - Tokunaga, Kazutoshi

AU - Satow, T.

AU - Yamazaki, K.

AU - Motojima, O.

PY - 2003/3/1

Y1 - 2003/3/1

N2 - 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.

AB - 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.

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JF - Journal of Nuclear Materials

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