Erosion from and deposition on JET divertor tiles used during the 2007–2009 campaign and on inner wall guard limiter (IWGL) tiles used during 2005–2009 are studied. The tungsten coating on the divertor tiles was mostly intact with the largest erosion ∼30% in a small local area. Locally high erosion areas were observed on the load bearing divertor tile 5 and on the horizontal surface of the divertor tile 8. The IWGL tiles show a complicated distribution of erosion and deposition areas. The total amount of carbon deposited on the all IWGL tiles during the campaign 2005–2009 is estimated to be 65 g. The density of carbon deposits is estimated to be 0.67–0.83 g/cm3.
|Number of pages||4|
|Journal||Journal of Nuclear Materials|
|Publication status||Published - 2013|
|MoE publication type||A1 Journal article-refereed|
|Event||20th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices - Aachen, Aachen, Germany|
Duration: 21 May 2012 → 25 May 2012