Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials

S. Wurster, N. Baluc, M. Battabyal, T. Crosby, J. Du, C. García-Rosales, A. Hasegawa, A. Hoffmann, A. Kimura, H. Kurishita, R. J. Kurtz, H. Li, S. Noh, J. Reiser, J. Riesch, M. Rieth, W. Setyawan, M. Walter, J. H. You, R. Pippan

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238 Citations (Scopus)


Tungsten materials are candidates for plasma-facing components for the International Thermonuclear Experimental Reactor and the DEMOnstration power plant because of their superior thermophysical properties. Because these materials are not common structural materials like steels, knowledge and strategies to improve the properties are still under development. These strategies discussed here, include new alloying approaches and microstructural stabilization by oxide dispersion strengthened as well as TiC stabilized tungsten based materials. The fracture behavior is improved by using tungsten laminated and tungsten wire reinforced materials. Material development is accompanied by neutron irradiation campaigns. Self-passivation, which is essential in case of loss-of-coolant accidents for plasma facing materials, can be achieved by certain amounts of chromium and titanium. Furthermore, modeling and computer simulation on the influence of alloying elements and heat loading and helium bombardment will be presented.

Original languageEnglish
Pages (from-to)S181-S189
JournalJournal of Nuclear Materials
Issue number1-3 SUPPL.1
Publication statusPublished - 2013

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering


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