The design of the ITER first wall panels

R. Mitteau (1, 2) , B. Calcagno (2) , P. Chappuis (1, 2) , R. Eaton (2) , S. Gicquel (2) , C. Jiming (3) , A. Labusov (4) , A. Martin (2) , M. Merola (2) , R. Raffray (2) , M. Ulrickson (5) , F. Zacchia (6)

1 IRFM - Institut de Recherche sur la Fusion par confinement Magnétique
2 ITER - ITER organization
3 SWIP - Southwestern Institute of Physics
4 Efremov Research Institute
5 SNL - Sandia National Laboratories [Albuquerque]
6 Fusion for Energy, Barcelona

The ITER blanket is in the final stage of design completion. The issues raised during the 2007 ITER design review about the First Wall (FW) heat loads and remote handling strategy have been addressed, while integrating the recently confirmed in-vessel coils. This paper focuses on the FW design, which is nearing completion. Key design justifications are presented, followed by a summary of the current status of the manufacturing plan and R&D activities.

Keywords: Blanket; Plasma facing component; Design; Heat loads; ITER; Wall; Limiter

Domains: Plasma Physics [physics.plasm-ph]

R. Mitteau, B. Calcagno, P. Chappuis, R. Eaton, S. Gicquel, et al.. The design of the ITER first wall panels. Fusion Engineering and Design, 2013, 88 (6-8), pp.568 - 570. ⟨10.1016/j.fusengdes.2013.05.030⟩. ⟨cea-02922289⟩