English
 
User Manual Privacy Policy Disclaimer Contact us
  Advanced SearchBrowse

Item

ITEM ACTIONSEXPORT

Released

Journal Article

Plasma facing and high heat flux materials - needs for ITER and beyond

MPS-Authors
/persons/resource/persons108745

Bolt,  H.
Material Research (MF), Max Planck Institute for Plasma Physics, Max Planck Society;

/persons/resource/persons108614

Barabash,  V.
Material Research (MF), Max Planck Institute for Plasma Physics, Max Planck Society;

/persons/resource/persons110287

Roth,  J.
Material Research (MF), Max Planck Institute for Plasma Physics, Max Planck Society;

External Ressource
No external resources are shared
Fulltext (public)
There are no public fulltexts stored in PuRe
Supplementary Material (public)
There is no public supplementary material available
Citation

Bolt, H., Barabash, V., Federici, G., Linke, J., Loarte, A., Roth, J., et al. (2002). Plasma facing and high heat flux materials - needs for ITER and beyond. Journal of Nuclear Materials, 307, 43-52.


Cite as: http://hdl.handle.net/11858/00-001M-0000-0027-417B-1
Abstract
Plasma-facing materials (PFMs) have to withstand particle and heat loads from the plasma and neutron loads during reactor operation. For ITER knowledge has been accumulated by operation experience and dedicated tests in present tokamaks as well as by laboratory experiments and modelling. The rationale for the selection of PFMs in ITER (Be, W, carbon fibre reinforced carbon) is described with regard to the critical issues concerning PFMs, esp. erosion during transient heat loads and the T-inventory in connection with the redeposition of carbon. In the fusion reactor generation after ITER the very stringent conditions of increased surface power to be removed from the plasma, a lifetime requirement of several operational years, high neutron fluences and increased operation temperature are exerting even more severe constraints on the selection of possible materials. Comparing these boundary conditions with materials under development and their further potential, only a narrow path is left regarding heat sink and PFMs. In this context the investigations on W as first wall material carried out e.g. in ASDEX Upgrade are being discussed as well as laboratory results on W-based material systems. The implications of these results are the starting point of what should form a consistent programme towards plasma-facing and heat sink materials for a fusion reactor. (C) 2002 Elsevier Science B.V. All rights reserved.