ITER vacuum vessel, in-vessel components and plasma facing materials

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Abstract

The vacuum vessel (VV) design is being developed in more detail considering manufacturing and assembly methods, and cost. Incorporating manufacturing studies being performed in cooperation with ITER Parties, the regular VV sector design has been nearly finalized. Design of the neutral beam (NB) ports including duct liners has been developed. Design of the in-wall shielding has been developed in more detail considering the supporting structure and the assembly method. Additional ferromagnetic inserts to be installed in the outboard midplane region will minimize the maximum ripple and the toroidal field flux line fluctuation. Detailed studies were carried out on the ITER vacuum vessel to define appropriate codes and standards in the context of ITER licensing in France. The blanket module design has progressed in cooperation with participant teams. Fabrication of mock-ups for qualification testing is under way and the tests will be performed in 2007-2008. The divertor activities have progressed with the aim of launching the procurement according to the ITER project schedule. © 2008.

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Ioki, K., Barabash, V., Cordier, J., Enoeda, M., Federici, G., Kim, B. C., … Yu, J. (2008). ITER vacuum vessel, in-vessel components and plasma facing materials. Fusion Engineering and Design, 83(7–9), 787–794. https://doi.org/10.1016/j.fusengdes.2008.05.027

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