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(ITER/5) ITER-FEAT Vacuum Vessel and Blanket Design Features and Implications for the R&D Programme

K. Ioki¹⁾, W. Daenner²⁾, K. Koizumi³⁾, V. Krylov⁴⁾, A. Cardella¹⁾, F. Elio¹⁾, M. Onozuka¹⁾, ITER Joint Central Team and Home Teams
 
¹⁾ ITER Joint Central Team, Garching Joint Work Site, Garching, Germany
²⁾ EU Home Team, EFDA CSU, Max-Planck Institute, Garching, Germany
³⁾ JA Home Team, Japan Atomic Energy Research Institute (JAERI), Japan
⁴⁾ RF Home Team, Efremov Institute, St. Petersburg, Russian Federation

Abstract.  A tight fitting configuration of the VV to the plasma aids the passive plasma vertical stability, and ferromagnetic material in the VV reduces the TF ripple. The blanket modules are supported directly by the VV. A full-scale VV sector model has provided critical information related to fabrication technology, and the magnitude of welding distortions and achievable tolerances. This R&D validated the fundamental feasibility of the double-wall VV design. The blanket module configuration consists of a shield body to which a separate first wall is mounted. The separate first wall has a facet geometry consisting of multiple flat panels, where 3-D machining will not be required. A configuration with deep slits minimizes the induced eddy currents and loads. The feasibility and the robustness of solid HIP joining was demonstrated in R&D, by manufacturing and testing several small and medium scale mock-ups and finally two prototypes. Remote handling tests and assembly tests of a blanket module have demonstrated the basic feasibility of its installation and removal.

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