Operational conditions in a W-clad tokamak

• Published in: Journal of nuclear materials Vol. 367; pp. 1497 - 1502
• Main Authors: Neu, R., Hopf, Ch, Kallenbach, A., Pütterich, T., Dux, R., Greuner, H., Gruber, O., Herrmann, A., Krieger, K., Maier, H., Rohde, V.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01-08-2007; Elsevier
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Installations for energy generation and conversion: thermal and electrical energy; Tokamak; Nuclear fusion reactor; Protective coatings; Tungsten; Plasma facing component; Fusion reactor divertors
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2007.04.018

Experiments with tungsten plasma facing components (PFCs) are performed in the ASDEX Upgrade divertor tokamak and the area covered by W-PFCs has been increased steadily since 1999 reaching 85% for the 2005/2006 campaign. The configurations chosen are W-coatings on graphite and CFC. The different locations are subject to different power loads and erosion yields. This is taken into account by selecting different thicknesses in the W-coating manufactured either by physical vapour deposition or vacuum plasma spraying. Power loads in excess of 15
MW/m
2 can be handled in this way. The experiments on ASDEX Upgrade show that plasma operation is feasible with walls and divertor surfaces mostly covered with tungsten, but also reveal critical issues: fast particles from plasma heating can play a crucial role in W erosion and particle transport must be kept high enough to overcome high impurity content and to prevent central impurity accumulation.