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Development of advanced high heat flux and plasma-facing materials

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

Abstract:
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

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Verlagsausgabe §
DOI: 10.5445/IR/1000078004
Veröffentlicht am 20.12.2017
Originalveröffentlichung
DOI: 10.1088/1741-4326/aa6f71
Scopus
Zitationen: 100
Web of Science
Zitationen: 93
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
urn:nbn:de:swb:90-780041
KITopen-ID: 1000078004
HGF-Programm 31.03.09 (POF III, LK 01)
Strukturmaterial f. Blanket und Divertor
Erschienen in Nuclear fusion
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 Scopus
Web of Science
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