ITER-FEAT vacuum vessel and blanket design features and implications for the R&D programme

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.

Overview of ITER-FEAT - The future international burning plasma experiment

“…Whilst the new design of ITER [17][18][19][20][21][22] uses, as far as possible, technical solutions and concepts previously developed and qualified for the 1998 ITER design, the changes in overall scale and in some physics requirements (e.g., more plasma shaping) and the pressure to preserve the plasma performance capacity and flexibility, whilst approaching the 50% cost savings target, have induced some significant changes in the design features.…”

Model and simulation of a vacuum sieve tray for T extraction from liquid PbLi breeding blankets

“…The VST extraction system then operates purely passively under the influence of gravity (the hydrostatic pressure is the only driving force). The total height of the tritium extraction system was set to 10 m, which is considered to be a conservative value, even regarding the dimensions of ITER [28]. It can be subdivided over two different contributions: (i) the height of PbLi reservoir h PbLi above the nozzle array which will define the hydrostatic pressure at the nozzle outlets and (ii) the height of the vacuum tank h VT .…”

“…Figure7: The considered VST implementation in the second method to reduce the vacuum tank size. The height of the vacuum vessel containing the plasma is comparable to the one designed for ITER[28].…”

ITER nuclear components, preparing for the construction and R&D results

“…1) of SS 316L(N)-IG (ITER Grade) [1]. The main vessel consists of inner and outer shells, poloidal and toroidal ribs and in-wall shielding.…”