期刊
FUSION ENGINEERING AND DESIGN
卷 82, 期 15-24, 页码 1706-1712出版社
ELSEVIER SCIENCE SA
DOI: 10.1016/j.fusengdes.2007.05.022
关键词
JET; first wall tiles; beryllium; hot spot melting; castellations; eddy currents
Work is in progress to completely replace, in 2008/9, the existing JET CFC tiles with a configuration of plasma facing materials consistent with the ITER design. The ITER-like wall (ILW) will be created with a combination of beryllium (Be), tungsten (W), W-coated CFC and Be-coated inconel tiles, with the material depending on the local anticipated heat flux and geometry. Over 4000 tiles will be replaced and the ILW will accommodate additional heating up to at least 50 MW for 10 s. One of the objectives is to maintain or improve the existing CFC tile power handling performance which has been achieved in most cases by hiding bolt holes, optimising tile size and profile and introducing castellations on plasma facing surfaces. This paper describes the generic problems associated with the Be tiles (power handling capacity and disruption induced eddy currents) and illustrates the solution selected for the inner wall guard limiter (IWGL) where the present CFC tiles will be replaced with Be. (c) 2007 Elsevier B.V. All rights reserved.
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