Fusion Technology · 1994 · 10 citations · 10 references
EngineeringNuclear EngineeringPhysicsFusion EngineeringNuclear MaterialsPlasma PhysicsDivertor DesignDivertor EngineeringFusion Reactor MaterialsMaterial DegradationMaterial Degradation AssessmentPlasma-wall InteractionsDivertor Lifetime AssessmentDivertor MaterialsDivertor PhysicsDivertor Target MaterialsPlasma ComponentsPlasma Facing ComponentsPlasma-facing MaterialsTarget Plate Materials
Divertor materials erosion and lifetime is a critical issue in designing plasma-facing components (PFCs) for ITER. Currently, three materials are considered as candidates to be used for the divertor target plate, namely, beryllium, carbon and tungsten. In this paper, major issues associated with the use of these candidates are reviewed and relevant data obtained from recent PISCES experiments will be discussed with the main emphasis on the wall lifetime issue.
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