(OV/5-4) Status of R&D Activities on Materials for Fusion Power Reactors

N. Baluc1), K. Abe2), J.L. Boutard3), V.M. Chernov4), E. Diegele3), S. Jitsukawa5), A. Kimura6), R.L. Klueh7), A. Kohyama6), R.J. Kurtz8), R. Lässer3), H. Matsui9), A. Möslang10), T. Muroga11), G.R. Odette12), M.Q. Tran13), B. van der Schaaf14), Y. Wu15), J. Yu16), S.J. Zinkle7)
1) CRPP-EPFL, Villigen, Switzerland
2) Department of Quantum Science and Energy Engineering, Tohoku University, Sendai, Japan
3) EFDA CSU, Garching, Germany
4) Bochvar Research Institute of Inorganic Materials, Moscow, Russia
5) JAEA, Tokyo, Japan
6) IAE, Kyoto University, Kyoto, Japan
7) ORNL, Oak Ridge, USA
8) PNNL, Richland, USA
9) Institute of Materials Research, Tohoku University, Sendai, Japan
10) FZK, IMF-I, Karlsruhe, Germany
11) National Institute for Fusion Science, Gifu, Japan
12) UCSB, Santa Barbara, USA
13) CRPP-EPFL, Lausanne, Switzerland
14) NRG, Petten, The Netherlands
15) Institute of Plasma Physics, Hefei, P.R. China
16) CIAE, Beijing, P.R. China

Abstract.  Current R&D activities on materials for fusion power reactors are mainly focused on plasma facing, structural and tritium breeding materials for plasma facing (first wall, divertor) and breeding blanket components. Most of these activities are being performed in Europe, Japan, P.R. China, Russia and the USA. They relate to development of new high temperature, radiation resistant materials, development of coatings that shall act as erosion, corrosion, permeation, electrical or MHD barriers, characterization of the whole candidate materials in terms of mechanical and physical properties, assessment of irradiation effects, compatibility experiments, development of reliable joints, and development and/or validation of design rules. Priorities defined worldwide in the field of materials for fusion power reactors will be summarized, as well as the main achievements obtained during the last few years and the near-term perspectives in the different investigation areas.

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