2022-07-21 - The coil production line in the 250-metre, on-site production facility where the European Domestic Agency for ITER, Fusion for Energy, is producing four poloidal field coils. Two have been finalized (including one already installed in the Tokamak pit) and two others are in the last stages of production.

Following a decision made at the ITER Council in November 2013, two types of in-vessel coils (IVCs), namely, edge-localized mode (ELM) coils to mitigate ELMs and vertical stability (VS) coils to provide vertical stabilization of the plasma, have been …

2010年12月23日 · In this paper, the up-to-date design of the PF coils and each sub-component such as winding pack, electrical insulation, joints and terminations, helium inlet, jumpers, and coils' supports are discussed together with their fabrication methods. ITER magnets are all designed using superconducting conductors with a high current carrying capability.

The ITER project is considering the inclusion of two sets of in-vessel coils, one to mitigate the effect of Edge Localized Modes (ELMs) and another to provide vertical stabilization (VS). The in-vessel location (behind the blanket shield modules, mounted to the vacuum vessel inner wall) presents special challenges in terms of

2011年11月3日 · The ITER Poloidal Field (PF) magnet system consists of six coils. Niobium-Titanium (NbTi) is used as superconducting material and cable-in-conduit conductor(CICC) type are used as a conductor. All coils are fabricated by stacking 6 to 9 double-pancakes wound by two-in-hand winding scheme.

2011年7月1日 · The ITER poloidal field (PF) coil system provides a magnetic field for plasma shaping and position control together with the central solenoid coils; it needs to operate in a fast...

2010年10月25日 · The ITER in-vessel coil system is comprised of two systems: the vertical stability coils and the edge localized mode (ELM) coils. The vertical stability coils are two poloidal field coils located above and below the tokamak's mid-plane. They provide fast vertical stabilization of the plasma.

2005年11月1日 · Design optimisation of the ITER TF coil cases and associated structures has been successful to reduce manufacturing requirements on the coils (in terms of component thicknesses and NDT inspection criteria) while satisfying a rigorous design code suitable for the operation of large metallic structures under intense fatigue conditions.

2025年3月17日 · On 30-31 January, the ITER In-Vessel Assembly Project conducted a comprehensive review of the assembly and installation processes for key in-vessel components, including the in-vessel coils and the blanket and divertor systems. The initiative aimed to review the installation activities by optimizing the sequence, tools, and logic underpinning these critical installation activities, which are ...

2019年9月1日 · ITER In-Vessel Coils (IVCs), resistive magnets to be installed in close proximity to ITER plasma to compensate fast perturbations of the plasma itself, have undergone a comprehensive revision of their requirements and operational loads, leading to design modifications and R&D activities.