Oxidation for deposits removal and hydrogen release on HT-7

J. S. Hu; J. G. Li; X. M. Wang; Y. P. Zhao

doi:10.1016/j.jnucmat.2007.01.286

Oxidation for deposits removal and hydrogen release on HT-7

J. S. Hu
, J. G. Li
, X. M. Wang
, Y. P. Zhao

School of Electrical Engineering

CAS - Institute of Plasma Physics

Research output: Contribution to journal › Article › peer-review

22 Scopus citations

Abstract

Oxidation experiments at wall temperatures of 400-470 K, including O-ICR, O-GDC conditioning and thermal-oxidation have been carried out for removal of deposits and hydrogen in HT-7. Thermal-oxidation seems ineffective to remove co-deposited layers and hydrogen at these temperatures. O-GDC oxidation appeared to be the most efficient on HT-7. However O-ICR was almost as good and could be applied with the magnetic field in ITER. Both O-ICR and O-GDC have a deposits removal rates ∼20 times that of He-ICR and He-GDC cleaning. Higher pressures and conditioning power during oxygen wall conditioning are favorable for removal of deposits and hydrogen. The oxygen retention after O-GDC oxidations was much higher than that after O-ICR oxidations. High power low oxygen pressure and He in O-ICR oxidation are beneficial for reducing oxygen retention. To remove the retained oxygen on walls both He-ICR and He-GDC were found to be effective. Plasma discharges could be recovered after a few tens of disruptive plasmas.

Original language	English
Pages (from-to)	862-869
Number of pages	8
Journal	Journal of Nuclear Materials
Volume	363-365
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2007.01.286
State	Published - 15 Jun 2007

Keywords

Co-deposition
ICRF
Oxygen
Tritium
Wall conditioning

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10.1016/j.jnucmat.2007.01.286

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title = "Oxidation for deposits removal and hydrogen release on HT-7",

abstract = "Oxidation experiments at wall temperatures of 400-470 K, including O-ICR, O-GDC conditioning and thermal-oxidation have been carried out for removal of deposits and hydrogen in HT-7. Thermal-oxidation seems ineffective to remove co-deposited layers and hydrogen at these temperatures. O-GDC oxidation appeared to be the most efficient on HT-7. However O-ICR was almost as good and could be applied with the magnetic field in ITER. Both O-ICR and O-GDC have a deposits removal rates ∼20 times that of He-ICR and He-GDC cleaning. Higher pressures and conditioning power during oxygen wall conditioning are favorable for removal of deposits and hydrogen. The oxygen retention after O-GDC oxidations was much higher than that after O-ICR oxidations. High power low oxygen pressure and He in O-ICR oxidation are beneficial for reducing oxygen retention. To remove the retained oxygen on walls both He-ICR and He-GDC were found to be effective. Plasma discharges could be recovered after a few tens of disruptive plasmas.",

keywords = "Co-deposition, ICRF, Oxygen, Tritium, Wall conditioning",

author = "Hu, \{J. S.\} and Li, \{J. G.\} and Wang, \{X. M.\} and Zhao, \{Y. P.\}",

year = "2007",

month = jun,

day = "15",

doi = "10.1016/j.jnucmat.2007.01.286",

language = "英语",

volume = "363-365",

pages = "862--869",

journal = "Journal of Nuclear Materials",

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TY - JOUR

T1 - Oxidation for deposits removal and hydrogen release on HT-7

AU - Hu, J. S.

AU - Li, J. G.

AU - Wang, X. M.

AU - Zhao, Y. P.

PY - 2007/6/15

Y1 - 2007/6/15

N2 - Oxidation experiments at wall temperatures of 400-470 K, including O-ICR, O-GDC conditioning and thermal-oxidation have been carried out for removal of deposits and hydrogen in HT-7. Thermal-oxidation seems ineffective to remove co-deposited layers and hydrogen at these temperatures. O-GDC oxidation appeared to be the most efficient on HT-7. However O-ICR was almost as good and could be applied with the magnetic field in ITER. Both O-ICR and O-GDC have a deposits removal rates ∼20 times that of He-ICR and He-GDC cleaning. Higher pressures and conditioning power during oxygen wall conditioning are favorable for removal of deposits and hydrogen. The oxygen retention after O-GDC oxidations was much higher than that after O-ICR oxidations. High power low oxygen pressure and He in O-ICR oxidation are beneficial for reducing oxygen retention. To remove the retained oxygen on walls both He-ICR and He-GDC were found to be effective. Plasma discharges could be recovered after a few tens of disruptive plasmas.

AB - Oxidation experiments at wall temperatures of 400-470 K, including O-ICR, O-GDC conditioning and thermal-oxidation have been carried out for removal of deposits and hydrogen in HT-7. Thermal-oxidation seems ineffective to remove co-deposited layers and hydrogen at these temperatures. O-GDC oxidation appeared to be the most efficient on HT-7. However O-ICR was almost as good and could be applied with the magnetic field in ITER. Both O-ICR and O-GDC have a deposits removal rates ∼20 times that of He-ICR and He-GDC cleaning. Higher pressures and conditioning power during oxygen wall conditioning are favorable for removal of deposits and hydrogen. The oxygen retention after O-GDC oxidations was much higher than that after O-ICR oxidations. High power low oxygen pressure and He in O-ICR oxidation are beneficial for reducing oxygen retention. To remove the retained oxygen on walls both He-ICR and He-GDC were found to be effective. Plasma discharges could be recovered after a few tens of disruptive plasmas.

KW - Co-deposition

KW - ICRF

KW - Oxygen

KW - Tritium

KW - Wall conditioning

UR - https://www.scopus.com/pages/publications/34248595974

U2 - 10.1016/j.jnucmat.2007.01.286

DO - 10.1016/j.jnucmat.2007.01.286

M3 - 文章

AN - SCOPUS:34248595974

SN - 0022-3115

VL - 363-365

SP - 862

EP - 869

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3

ER -

Oxidation for deposits removal and hydrogen release on HT-7

Abstract

Keywords

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