The Toroidal Field Coils for the ITER Project

Savary, F.; Gallix, R.; Knaster, J.; Mitchell, N.; Seo, K.

doi:10.1109/tasc.2011.2174561

Cited by 11 publications

(6 citation statements)

References 9 publications

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“…In this section, the geometry of a D-shaped coil, used in Tokamak fusion devices, is investigated [46,47]. The shape and dimensions of the coil are shown in figure 15 (design parameters presented in [48]).…”

Section: D-shape Coil Model and Analysismentioning

confidence: 99%

3D homogenization of the T-A formulation for the analysis of coils with complex geometries

Vargas-Llanos

Huber²,

Riva³

et al. 2022

Supercond. Sci. Technol.

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The modeling and analysis of superconducting coils is an essential task in the design stage of most devices based on high-temperature superconductors (HTS). These calculations allow verifying basic estimations and assumptions, proposing improvements, and computing quantities that are not easy to calculate with an analytical approach. For instance, the estimation of losses in HTS is fundamental during the design stage since losses can strongly inﬂuence the cooling system requirements and operating temperature. Typically, 2D ﬁnite element analysis is used to calculate AC losses in HTS, due to the lack of analytical solutions that can accurately represent complex operating conditions such as AC transport current and AC external applied magnetic ﬁeld in coils. These 2D models are usually a representation of an inﬁnitely long arrangement. Therefore, they cannot be used to analyze end effects and complex 3D conﬁgurations. In this publication, we use the homogenization of the T-A formulation in 3D for the analysis of superconducting coils with complex geometries where a 2D approach can not provide accurate analyses and veriﬁcation of assumptions. The modeling methodology allows an easier implementation in commercial software (COMSOL Multiphysics) in comparison with the currently available 3D H homogenization, despite the complexity of the geometry. This methodology is ﬁrst validated with a racetrack coil (benchmark case) by comparing the results with the well-established H formulation. Then, the electromagnetic behavior of coils with more complex geometries is analyzed.

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Section: D-shape Coil Model and Analysismentioning

confidence: 99%

3D homogenization of the T-A formulation for the analysis of coils with complex geometries

Vargas-Llanos

Huber²,

Riva³

et al. 2022

Supercond. Sci. Technol.

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“…The TF coil case encloses the winding pack and is the main structural component of the magnet system [6]. The TF coil inboard legs are wedged all along their side walls in operation, with friction playing an important role in supporting the out-of-plane magnetic forces.…”

Section: System Overview and Integrationmentioning

confidence: 99%

“…However, direct measurement of the locus of the current center line is expected to be possible at room temperature with a small AC current in the coil to an accuracy better than 1 mm. A prototype system is being developed [6].…”

Section: Assemblymentioning

confidence: 99%

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The ITER Magnets: Design and Construction Status

Mitchell

Devred

Libeyre

et al. 2012

IEEE Trans. Appl. Supercond.

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184

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The ITER magnet procurement is now well underway. The magnet systems consist of 4 superconducting coil sets (toroidal field (TF), poloidal field (PF), central solenoid (CS) and correction coils (CC)) which use both NbTi and -based conductors. The magnets sit at the core of the ITER machine and are tightly integrated with each other and the main vacuum vessel. The total weight of the system is about 10000 t, of which about 500 t are strands and 250 t, NbTi. The reaction of the magnetic forces is a delicate balance that requires tight control of tolerances and the use of high-strength, fatigue-resistance steel forgings. Integration and support of the coils and their supplies, while maintaining the necessary tolerances and clearance gaps, have been completed in steps, the last being the inclusion of the feeder systems. Twenty-one procurement agreements have now been signed with 6 of the ITER Domestic Agencies for all of the magnets together with the supporting feeder subsystems. All of them except one (for the CS coils) are so-called Build to Print agreements where the IO provides the detailed design including full three-dimensional CAD models. The production of the first components is underway (about 175 t of strand was finished by July 2011) and manufacturing prototypes of TF coil components are being completed. The paper will present a design overview and the manufacturing status.

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“…The ITER toroidal field (TF) system is formed by eighteen coils arranged around a torus shape that will provide a static field of 5.3 T at the plasma axis, with a peak field of ∼12 T at the inner leg, see figure 1(a). A detailed description of the toroidal field magnet system can be found in [1][2][3]. Each coil is composed of seven double pancakes (DP) inserted in a stainless steel case.…”

Section: Introductionmentioning

confidence: 99%

Performance assessment and optimization of the ITER toroidal field coil joints

Rolando

Foussat

Knaster³

et al. 2013

Supercond. Sci. Technol.

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The ITER toroidal field (TF) system features eighteen coils that will provide the magnetic field necessary to confine the plasma. Each winding pack is composed of seven double pancakes (DP) connected through praying hands joints. Shaking hands joints are used to interface the terminals of the conductor with the feeder and inter-coil U-shaped bus bars.The feasibility of operating plasma scenarios depends on the ability of the magnets to retain sufficient temperature and current margins. In this respect, the joints represent a possible critical region due to the combination of steady state Joule heating in the resistance of the joint and coupling losses and currents in ramped operation.The temperature and current margins of both DP and terminal joints are analysed during the 15 and 17 MA plasma scenarios. The effect on the joint performance of feasible optimization solutions, such as rotation of the terminal joints and sole RRR increase, is explored. The characterization of the TF coil joints is completed by the estimation of the coupling loss time constant for different inter-strand and strand-to-joint resistance values. The study is carried out with the code JackPot-ACDC, allowing the analysis of lap-type joints with a strand-level detail.

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The Toroidal Field Coils for the ITER Project

Cited by 11 publications

References 9 publications

3D homogenization of the T-A formulation for the analysis of coils with complex geometries

3D homogenization of the T-A formulation for the analysis of coils with complex geometries

The ITER Magnets: Design and Construction Status

Performance assessment and optimization of the ITER toroidal field coil joints

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