Development of advanced high heat flux and plasma-facing materials
Linsmeier, Ch; Rieth, M.
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.;
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.; 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
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
| 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 |
| 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 | Scopus Dimensions Web of Science |