Please note that eDoc will be permanently shut down in the first quarter of 2021!      Home News About Us Contact Contributors Disclaimer Privacy Policy Help FAQ

Home
Search
Quick Search
Advanced
Fulltext
Browse
Collections
Persons
My eDoc
Session History
Login
Name:
Password:
Documentation
Help
Support Wiki
Direct access to
document ID:


          Institute: MPI für Plasmaphysik     Collection: Articles, Books, Inbooks     Display Documents



  history
ID: 15635.0, MPI für Plasmaphysik / Articles, Books, Inbooks
Plasma facing and high heat flux materials - needs for ITER and beyond
Authors:Bolt, H.; Barabash, V.; Federici, G.; Linke, J.; Loarte, A.; Roth, J.; Sato, K.
Language:English
Date of Publication (YYYY-MM-DD):2002
Title of Journal:Journal of Nuclear Materials
Journal Abbrev.:J. Nucl. Mater.
Volume:307
Start Page:43
End Page:52
Review Status:Peer-review
Audience:Experts Only
Abstract / Description: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.
External Publication Status:published
Document Type:Article
Communicated by:N. N.
Affiliations:MPI für Plasmaphysik/Materialforschung
External Affiliations:ITER, IT, JWS Garching, D-85748 Garching, Germany; EURATOM, Forschungszentrum Julich, IWV 2, D-52425 Julich, Germany; CSU Garching, EFDA, D-85748 Garching, Germany; Japan Atom Energy Res Inst, NBI Heating Lab, Ibaraki 3110193, Japan
Identifiers:ISI:000180647200006
ISSN:0022-3115
The scope and number of records on eDoc is subject to the collection policies defined by each institute - see "info" button in the collection browse view.