Research and development on plasma facing components for fusion reactors in JAEA

Suzuki, Satoshi; Ezato, Koichiro; Yokoyama, Kenji; Dairaku, Masayuki; Enoeda, Mikio; Tanigawa, Hisashi; Tsuru, Daigo; Seki, Yohji; Mori, Kensuke*; Nishi, Hiroshi; Hirose, Takanori; Akiba, Masato

This paper presents the present status of R&D activities on plasma facing components (PFCs) for fusion reactors, such as ITER and fusion demonstration reactor (DEMO). The PFCs as typified by divertor and first wall components are subjected to high heat flux and particle flux from fusion plasma. It is essential to have sufficient heat removal capability and robust structure against those loadings. JAEA has been carried out to develop the ITER-PFCs which consist of copper alloys and armor materials with high thermal conductivity, such as carbon fiber composites, tungsten and beryllium. The demonstration of the thermomechanical performance has successfully been made under close mutual cooperation between the participant countries of ITER. Currently, the activity on the development of the ITER-PFCs is in a qualification phase prior to the bulk production for construction. In JAEA, the R&Ds on the DEMO-PFCs is being made in parallel with the development activity of the ITER-PFCs.