کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
271179 | 504990 | 2014 | 5 صفحه PDF | دانلود رایگان |

• Power handling of beryllium plasma facing components exceeded expectations.
• Local beryllium melting from power handling experiments to test the design limits.
• Local beryllium melting from disruptions.
• No change observed for most of the tungsten and tungsten-coated components.
The JET ITER-like Wall (ILW) provides the same plasma facing component configuration as ITER during its active phase: beryllium in the main chamber and tungsten in the divertor. Moving from a carbon-based wall to an all metals wall requires some operational adjustment. The reduction in radiation at the plasma edge and in the divertor can lead to high power loads on the plasma facing components both in steady state and in transients and requires the development of radiative scenarios and the use of massive gas injection to mitigate disruptions. These tools are even more important now because an all metal wall is much less forgiving to thermal overloading the carbon based wall used to be. Here the impact of the first 11 months of operation on the ILW plasma facing components is discussed.
Journal: Fusion Engineering and Design - Volume 89, Issues 7–8, October 2014, Pages 1059–1063