Laser-based and thermal methods for fuel removal and cleaning of plasma-facing components
Laser-based and thermal methods for fuel removal and cleaning of plasma-facing components
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DOI：
10.1016/j.jnucmat.2011.01.119
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发表时间：
2011-08
影响因子：
3.1
通讯作者：
D. Ivanova;M. Rubel;V. Philipps;B. Schweer;M. Freisinger;A. Huber;N. Gierse;H. Penkalla;P. Petersson;T. Dittmar
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文献类型：
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作者：
D. Ivanova;M. Rubel;V. Philipps;B. Schweer;M. Freisinger;A. Huber;N. Gierse;H. Penkalla;P. Petersson;T. Dittmar
在TEXTOR和Tore Supra托卡马克上回收的碳和钨限制器上测试了两种原位燃料去除方法的效率：激光诱导共沉积物烧蚀和高温真空退火。用热脱附光谱、光学光谱、离子束分析、表面轮廓术和显微镜等方法对气相和表面进行了分析，结果表明：（1）烧蚀导致产生50 nm- 2μm的尘埃粒子，（2）烧蚀的挥发性产物在周围表面上发生冷凝，冷凝物中的D/C比在0.02-0.03之间;（iv）623 K退火70 h，释放出的氘量不超过10%;（v）900- 1300 K加热可有效去除氘。
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 50nm – 2μm; (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 623K for 70h results in release of not more than ∼10% of deuterium accumulated in plasma-facing components; (v) effective removal is reached by heating to 900–1300K.