A brief summary of the progress on the EFDA tungsten materials program

M. Rieth, S.L. Dudarev, S.M. Gonzalez de Vicente, J. Aktaa, T. Ahlgren, S. Antusch, D.E.J. Armstrong, M. Balden, N. Baluc, M.-F. Barthe, W.W. Basuki, M. Battabyal, C.S. Becquart, D. Blagoeva, H. Boldyryeva, J. Brinkmann, M. Celino, L. Ciupinski, J.B. Correia, A. De BackerC. Domain, E. Gaganidze, C. Garcia-Rosales, J. Gibson, M.R. Gilbert, S. Giusepponi, B. Gludovatz, H. Greuner, K. Heinola, T. Höschen, A. Hoffmann, N. Holstein, F. Koch, W. Krauss, H. Li, S. Lindig, J. Linke, Ch. Linsmeier, P. Lopez-Ruiz, H. Maier, J. Matejicek, T.P. Mishra, Musemma Kedir Muhammed, Alex Montecino Munoz, M. Muzyk, K. Nordlund, D. Nguyen-Manh, J. Opschoor, N. Ordas, T. Palacios, G. Pintsuk, R. Pippan, J. Reiser, J. Riesch, S.G. Roberts, L. Romaner, M. Rosiński, M. Sanchez, W. Schulmeyer, H. Traxler, A. Urena, J.G. van der Laan, L. Veleva, S. Wahlberg, M. Walter, T. Weber, T. Weitkamp, S. Wurster, Mazher Ahmed Yar, J.H. You, A. Zivelonghi

Research output: Contribution to journalConference articleResearchpeer-review

Abstract

The long-term objective of the European Fusion Development Agreement (EFDA) fusion materials programme is to develop structural and armor materials in combination with the necessary production and fabrication technologies for reactor concepts beyond the International Thermonuclear Experimental Reactor. The programmatic roadmap is structured into four engineering research lines which comprise fabrication process development, structural material development, armor material optimization, and irradiation performance testing, which are complemented by a fundamental research programme on ‘‘Materials Science and Modeling.’’ This paper presents the current research status of the EFDA experimental and testing investigations, and gives a detailed overview of the latest results on materials research, fabrication, joining, high heat flux testing, plasticity studies, modeling, and validation experiments. © 2013 Elsevier B.V. All rights reserved.
Original languageEnglish
JournalJournal of Nuclear Materials
Volume442
Issue number1-3, Suppl. 1
Pages (from-to)S173–S180
ISSN0022-3115
DOIs
Publication statusPublished - 2013
Externally publishedYes
Event15th international conference on fusion reactor materials - Charleston, SC, United States
Duration: 16 Oct 201122 Oct 2011
Conference number: 15

Conference

Conference15th international conference on fusion reactor materials
Number15
CountryUnited States
CityCharleston, SC
Period16/10/201122/10/2011

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