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Tungsten as first wall material in fusion devices

2007; Elsevier BV; Volume: 82; Issue: 5-14 Linguagem: Inglês

10.1016/j.fusengdes.2007.03.045

1873-7196

M. Kaufmann, R. Neu,

Magnetic confinement fusion research

The observation in JET of co-deposition of tritium with carbon has led to a broad discussion on the replacement of graphite by a high-Z material for the first wall coverage. Moreover, due to the high erosion rate, carbon plasma facing components (PFCs) appear to be unacceptable for a commercial fusion reactor. Research in this area has subsequently gained increased attention. This paper describes the status of investigations on the use of tungsten as a first wall material. It discusses on the physical side the plasma wall interaction, the transport of tungsten in the plasma boundary and in the core. As an intermediate step on the technological side, graphite is often coated with tungsten layers. For highly loaded surfaces in a fusion reactor finally bulk tungsten components will have to be developed.