Fuel removal from plasma-facing components by oxidation-based techniques. An overview of surface conditions after oxidation

JOURNAL OF NUCLEAR MATERIALS

卷:363

Article; Proceedings Paper

Rubel, M. J. ; De Temmerman, G. ; Sergienko, G. ; Sundelin, P. ; Emmoth, B. ; Philipps, V.

关键词: deuterium inventory;    retention;    surface analysis;    co-deposition;    TEXTOR;   

DOI  :  10.1016/j.jnucmat.2007.01.107

来源: Elsevier

【 摘 要 】

Oxygen-assisted fuel removal is reported for laboratory-prepared a-C:D films and for layers obtained by boronisation in a tokamak and then exposed to a helium-oxygen glow discharge in TEXTOR. Oxidation of thick mixed-material co-deposits under laboratory conditions is also presented. The essential results are following: (i) laboratory-prepared amorphous deuterated carbon (a-C:D) layers are decomposed efficiently by the HC-O-2 glow: D and C contents are decreased by a factor of 45-220 and 25-60, respectively; (ii) the same treatment of the boronised films leads to the release of D but no removal of carbon is observed; (iii) the thermal oxidation (at 300 degrees C in air under laboratory conditions) of co-deposits on PFC and probes exposed to the SOL reduces the D content by a factor of 4-5 after 2 h, whereas nearly complete fuel removal (98%) occurs after 10 h at 300 degrees C. The study shows that the fuel removal efficiency is dependent on the overall composition of the mixed layer. It is high from pure a-C:D films but distinctly less efficient from real co-deposits. (c) 2007 Elsevier B.V. All rights reserved.

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