Development of ITER TF Coil in Japan

Koizumi, N.; Matsui, K.; Hemmi, T.; Takano, Katsutoshi; Chida, Yutaka; Iguchi, Masahide; Nakajima, Hideo; Shimada, M.; Oosemochi, Koichi; Makino, Yoshinobu; Nagamoto, Yoshifumi; Esaki, Kayoko

doi:10.1109/tasc.2011.2176697

Cited by 10 publications

(5 citation statements)

References 7 publications

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“…As illustrated in Figure 3, the tokamak cryostat is 28 m tall and 29 m in diameter, which corresponds more or less to the size of the Jefferson memorial in Washington DC. The ITER magnet system is fully superconducting and includes 4 different types of coils (see Figure 4) [4]  18 Toroidal Field (TF) coils, located around the plasma chamber, to be manufactured in EU [5] and Japan [6],  a Central Solenoid (CS), made up of a stack of 6 modules and positioned at the machine centre, to be manufactured in the US [7],  6 Poloidal Field (PF) coils, surrounding the TF coils, whose manufacture is the responsibility of RF (for PF1) and EU (for PF2 to 6) [8],  9 pairs of Correction Coils (CCs), attached to the PF coils, to be manufactured in China [9].…”

Section: Iter Tokamak and Magnet Systemmentioning

confidence: 99%

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Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

170

118

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Taking the relay of the Large Hadron Collider (LHC) at CERN, ITER has become the largest project in applied superconductivity. In addition to its technical complexity, ITER is also a management challenge as it relies on an unprecedented collaboration of 7 partners, representing more than half of the world population, who provide 90% of the components as in-kind contributions. The ITER magnet system has a stored energy of 51 GJ and involves 6 of the ITER partners. The coils are wound from Cable-In-Conduit Conductors (CICCs) made up of superconducting and copper strands assembled into a fully transposed, rope-type cable, inserted into a conduit of butt-welded austenitic steel tubes. The conductors for the Toroidal Field (TF) and Central Solenoid (CS) coils require about 500 tons of Nb 3 Sn strands while the Poloidal Field (PF) and Correction Coil (CC) and busbar conductors need around 250 tons of Nb-Ti strands. The required amount of Nb 3 Sn strands far exceeds pre-existing industrial capacity and has called for a significant worldwide production scale up. The TF conductors are the first ITER components to be mass produced and are more than 50% complete. During its life time, the CS coil will have to sustain several tens of thousands of electromagnetic (EM) cycles to high current and field conditions, way beyond anything a large Nb 3 Sn coil has ever experienced. Following a comprehensive R&D program, a technical solution has been found for the CS conductor, which ensures stable performance versus EM and thermal cycling. Productions of PF, CC and busbar conductors are also underway. After an introduction to the ITER project and magnet system, we describe the ITER conductor procurements and the Quality Assurance/Quality Control programs that have been implemented to ensure production uniformity across numerous suppliers. Then, we provide examples of technical challenges that have been encountered and we present a status of ITER conductor production worldwide.

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Section: Iter Tokamak and Magnet Systemmentioning

confidence: 99%

“…The ITER magnet system is fully superconducting and includes four different types of coils (see figure 4) [4] • 18 toroidal field (TF) coils, located around the plasma chamber, to be manufactured in EU [5] and Japan [6],…”

Section: Iter Tokamak and Magnet Systemmentioning

confidence: 99%

Challenges and status of ITER conductor production

Devred

Backbier

Bessette

et al. 2014

Supercond. Sci. Technol.

170

118

View full text Add to dashboard Cite

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“…Consequently, a proper welding method was established. The details are described in [2,10]. The results of RP flatness after CP welding are shown in Fig.…”

Section: Radial Plate Fabrication and Cover Plate Weldingmentioning

confidence: 99%

Completion of all Winding Packs for ITER Toroidal Field Coils in Japan

Kajitani

Nakamoto

Suwa

et al. 2023

Plasma and Fusion Research

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In Japan, National Institutes for Quantum Science and Technology (QST) has the responsibility to develop nine toroidal field (TF) coils, each of which consists of a winding pack (WP) and coil case for the ITER project. The WP consists of seven double-pancakes (DPs), which consist of conductors inserted into D-shaped radial plates (RPs). Although a WP is significantly large (14 m high and 9 m wide), the position of the current center line of the WP must be controlled within a few millimeters. Therefore, numerous technical challenges arose in DP and WP manufacturing. Herein, in the RP manufacturing, the optimization of welding and machining procedures, and accurate manufacturing techniques were established. Subsequently, all RPs were fabricated around the flatness errors of 1 mm from the nominal. In cover plate (CP) welding, the welding procedure was optimized so that a good DP flatness after CP welding was achieved. In the WP insulation, by developing a method to insulate a WP while applying compression, the dimensions within errors of a few milli-meters is achieved in all of WPs. Consequently, all nine WPs were successfully completed for TF coils in Japan in March 2022.

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“…to increase the achievable field or flux, while minimizing the cost and/or required space. The strategy adopted relies on winding the conductor in layers 22 instead of pancakes like in ITER. In fact, this approach allows grading of both superconductor and steel cross-sections in the different layers based on the local conditions.…”

Section: Advances In Science and Technology To Meet Challengesmentioning

confidence: 99%

“…EAST [17] WEST [18] KSTAR [19] JT-60SA [20] ITER [21,22] Major radius (m) cable structure of Bi2212 CICC is a critical technology. ASIPP has carried out lots of R&D activities on Bi2212 strands for CFETR magnets [29].…”

Section: Itemmentioning

confidence: 99%

Superconductors for fusion: a roadmap

Mitchell

Zheng

Vorpahl³

et al. 2021

Supercond. Sci. Technol.

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With the first tokamak designed for full nuclear operation now well into final assembly (ITER), and a major new research tokamak starting commissioning (JT60SA), nuclear fusion is becoming a mainstream potential energy source for the future. A critical part of the viability of magnetic confinement for fusion is superconductor technology. The experience gained and lessons learned in the application of this technology to ITER and JT60SA, together with new and improved superconducting materials, is opening multiple routes to commercial fusion reactors. The objective of this roadmap is, through a series of short articles, to outline some of these routes and the materials/technologies that go with them.

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Development of ITER TF Coil in Japan

Cited by 10 publications

References 7 publications

Challenges and status of ITER conductor production

Challenges and status of ITER conductor production

Completion of all Winding Packs for ITER Toroidal Field Coils in Japan

Superconductors for fusion: a roadmap

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