Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 30 / Number 3P1 / Pages 289-299
Roma B. Mohanti, John G. Gilligan, Mohamed A. Bourham
Fusion Science and Technology / Volume 30 / Number 3P1 / Pages 289-299
Format:electronic copy (download)
Exposure to near normal surfaces of poloidal divertor target plate tiles is a limiting feature of the power handling capability of the tiles. The problems associated with the design of poloidal divertor tiles, with beryllium chosen as the tile material, and possible methods of solving the problem are discussed. Thermal two- and three-dimensional analyses are carried out for the assessment of relative merits in performance due to modifications to the surface. The power handling capability (time to reach melting temperature of beryllium) of the target plate tiles is presented for unswept and swept plasma cases. Results have shown that sweeping the plasma improves the power handling capability by a factor of up to 10.
Your cart is empty.
Home|Invoice Payment|Nuclear Links