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Development of advanced high heat flux and plasma-facing materials

Linsmeier, Ch; Rieth, M. ORCID iD icon 1; Aktaa, J. 1; Chikada, T.; Hoffmann, A.; Hoffmann, J. 1; Houben, A.; Kurishita, H.; Jin, X. 1; Li, M.; Litnovsky, A.; Matsuo, S.; Müller, A. von; Nikolic, V.; Palacios, T.; Pippan, R.; Qu, D. 1; Reiser, J. 1; Riesch, J.; ... mehr


Plasma-facing materials and components in a fusion reactor are the interface between the
plasma and the material part. The operational conditions in this environment are probably
the most challenging parameters for any material: high power loads and large particle and
neutron fluxes are simultaneously impinging at their surfaces. To realize fusion in a tokamak
or stellarator reactor, given the proven geometries and technological solutions, requires an
improvement of the thermo-mechanical capabilities of currently available materials. In its
first part this article describes the requirements and needs for new, advanced materials for the
plasma-facing components. Starting points are capabilities and limitations of tungsten-based
alloys and structurally stabilized materials. Furthermore, material requirements from the
fusion-specific loading scenarios of a divertor in a water-cooled configuration are described,
defining directions for the material development. Finally, safety requirements for a fusion
reactor with its specific accident scenarios and their potential environmental impact lead to
the definition of inherently passive materials, avoiding release of radioactive material through
... mehr

Verlagsausgabe §
DOI: 10.5445/IR/1000078004
Veröffentlicht am 20.12.2017
DOI: 10.1088/1741-4326/aa6f71
Zitationen: 198
Web of Science
Zitationen: 182
Zitationen: 191
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Zeitschriftenaufsatz
Publikationsjahr 2017
Sprache Englisch
Identifikator ISSN: 0029-5515, 1741-4326
KITopen-ID: 1000078004
HGF-Programm 31.03.09 (POF III, LK 01) Strukturmaterial f. Blanket und Divertor
Erschienen in Nuclear fusion
Verlag International Atomic Energy Agency (IAEA)
Band 57
Heft SI
Seiten Article no 092007
Schlagwörter plasma-facing materials, high heat flux materials, composites, tungsten-based, materials, passive safety, tritium permeation barriers, functionally graded materials
Nachgewiesen in Web of Science
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