September 19, 2007
Journal Article

Status of R&D Activities on Materials for Fusion Power Reactors

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 or electrical/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 are summarized, as well as the main achievements obtained during the last few years and the near-term perspectives in the different investigation areas.

Revised: July 30, 2009 | Published: September 19, 2007

Citation

Baluc N., K. Abe, J.L. Boutard, V.M. Chernov, E. Diegele, S. Jitsukawa, and A. Kimura, et al. 2007. Status of R&D Activities on Materials for Fusion Power Reactors. Nuclear Fusion 47, no. 10:S696-S717. PNNL-SA-52989. doi:10.1088/0029-5515/47/10/S18