Laser-based and thermal methods for fuel removal and cleaning of plasma-facing components

被引：22
作者：
Ivanova, D. [1 ]
Rubel, M. [1 ]
Philipps, V. [2 ]
Schweer, B. [2 ]
Freisinger, M. [2 ]
Huber, A. [2 ]
Gierse, N. [2 ]
Penkalla, H. [2 ]
Petersson, P. [3 ]
Dittmar, T. [4 ]
机构：
[1] Royal Inst Technol, Alfven Lab, Assoc EURATOM VR, Stockholm, Sweden
[2] Forschungszentrum Julich, Inst Energy Res 4, EURATOM Assoc, D-52425 Julich, Germany
[3] Uppsala Univ, Angstrom Lab, Assoc EURATOM VR, Uppsala, Sweden
[4] Assoc EURATOM CEA, CEA Cadarache, IRFM, St Paul Les Durance, France
来源：
JOURNAL OF NUCLEAR MATERIALS | 2011年 / 415卷 / 01期
关键词：
RETENTION;
D O I：
10.1016/j.jnucmat.2011.01.119
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The efficiency of two methods for in situ fuel removal has been tested on carbon and tungsten limiters retrieved from the TEXTOR and Tore Supra tokamaks: laser-induced ablation of co-deposits and annealing in vacuum at elevated temperature. The analyses of gas phase and surfaces performed with thermal desorption spectrometry, optical spectroscopy, ion beam analysis, surface profilometry and microscopy methods have shown: (i) the ablation leads to the generation of dust particles of 50 nm - 2 mu m; (ii) volatile products of ablation undergo condensation on surrounding surfaces; (iii) D/C ratio in such condensate is in the range 0.02-0.03; (iv) long-term annealing of 623 K for 70 h results in release of not more than 10% of deuterium accumulated in plasma-facing components; (v) effective removal is reached by heating to 900-1300 K. (C) 2011 Published by Elsevier B.V.
引用
收藏
页码：S801 / S804
页数：4
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