JT-60SA superconducting magnet system

Koide, Y.; Yoshida, Kiyoshi; Wanner, M.; Barabaschi, P.; Cucchiaro, A.; Davis, S.; Decool, P.; Pietro, E. Di; Disset, G.; Genini, L.; Hajnal, N.; Heller, R.; Honda, Akira; Ikeda, Yujiro; Kamada, Y.; Kashiwa, Y.; Kizu, K.; Kamiya, Kōji; Murakami, Haruyuki; Michel, Frédéric; Maréchal, J. L.; Phillips, G.; Polli, Gian Mario; Rossi, Paolo; Shibanuma, Kiyoshi; Takahata, K.; Tomarchio, Valerio; Tsuchiya, Kazuyoshi; Usui, K.; Verrecchia, M.; Zani, L.

doi:10.1088/0029-5515/55/8/086001

Cited by 30 publications

(3 citation statements)

References 16 publications

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“…The poloidal field coil system of JT-60SA is made up of six EF coils (EF1~EF6) of different sizes and four identical CS modules (CS1~CS4), both of which are procured by Japan [26]. The former uses NbTi CICC (outer dimensions: 25×25 mm 2 and 27.7×27.7 mm 2 ), and the latter Nb 3 Sn CICC (outer dimensions: 27.9×27.9 mm 2 ).…”

Section: Magnetsmentioning

confidence: 99%

Recent progress of the JT-60SA project

Shirai

Barabaschi²,

Kamada

2017

Nucl. Fusion

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The JT-60SA project has been implemented for the purpose of an early realization of fusion energy. With a powerful and versatile NBI and ECRF system, a flexible plasma-shaping capability, and various kinds of in-vessel coils to suppress MHD instabilities, JT-60SA plays an essential role in addressing the key physics and engineering issues of ITER and DEMO. It aims to achieve the long sustainment of high integrated performance plasmas under the high βN condition required in DEMO. The fabrication and installation of components and systems of JT-60SA procured by the EU and Japan are steadily progressing. The installation of toroidal field (TF) coils around the vacuum vessel started in December 2016. The commissioning of the cryogenic system and power supply system has been implemented in the Naka site, and JT-60SA will start operation in 2019. The JT-60SA research plan covers a wide area of issues in ITER and DEMO relevant operation regimes, and has been regularly updated on the basis of intensive discussion among European and Japanese researchers.

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Section: Magnetsmentioning

confidence: 99%

Recent progress of the JT-60SA project

Shirai

Barabaschi²,

Kamada

2017

Nucl. Fusion

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“…The poloidal field coil system of JT-60SA is made up of six different EFCs (EF1-EF6) and four identical CS modules (CS1-CS4), which are procured by Japan [12]. The former uses NbTi CICC (outer dimensions: 25 × 25 mm 2 and 27.7 × 27.7 mm 2 ), and the latter Nb 3 Sn CICC (outer dimensions: 27.9 × 27.9 mm 2 ).…”

Section: Poloidal Field Coilsmentioning

confidence: 99%

Progress of JT-60SA Project: EU-JA joint efforts for assembly and fabrication of superconducting tokamak facilities and its research planning

Shirai

Barabaschi²,

Kamada

2016

Fusion Engineering and Design

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“…As a consequence of their status of merits drivers, the magnets are continuously investigated either on R&D or on more upstream grounds. In fusion domain the Cable-in-Conduit Conductors (CICC) technology [1] is routinely considered in the magnet systems of actual tokamaks ( [2][3] [4]). While providing assessed advantages (among other, coolant confinement, efficient strands wetting, solid structural reinforcement…) the concept remains challenging regarding its accurate modelling using its design characteristics only towards predicting Manuscript received 27 October 2020.…”

Section: Introductionmentioning

confidence: 99%

Extensive Analyses of Superconducting Cables 3D Geometry With Advanced Tomographic Examinations

Zani

Tiseanu²,

Chiletti³

et al. 2021

IEEE Trans. Appl. Supercond.

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In the framework of activities embedding magnet design and associated R&D activities and relying on Cable in Conduit Conductors (CICC) technology, the singularity of the concept can rise some challenges versus their modelling in operation. Indeed, CICC includes thousands of superconducting strands, twisted together under a multi-staged scheme that also includes deformation by cabling and compaction during manufacture. This causes the accurate predictability of strands position in CICC extremely difficult, while it can be a key element for modelling their performances in operation. As a matter of fact the coupling losses rely on the CICC capability to establish interstrand shielding currents, driven by the inter-strand contacts mapping which are only accessible in prediction via accurate 3D strand trajectories geometry. Same applies for prediction of CICC mechanical properties (deformation of Nb3Sn strands) and hydraulic properties (helium coolant force-flowed between the strands), making those investigations of high added-value. In this context, INFLPR installed a new set-up dedicated to micro-tomography that is able to examine CICCs with high resolution, allowing to get an overall overall 3D overview regarding picture of the strands location. CEA and INFLPR further developed a post-processing method to reconstruct the strands trajectories with high accuracy. The measurement and data analysis workflow was applied to two middle-size CICCs with variable void fraction from which statistics of contacts were issued. The obtained database was exploited to reconstruct equivalent 3D resistive network, in view of interpreting coupling losses tests with help of analytic CEA model (COLISEUM) based on multi-stage representation.The above applications using CICC topology database will be discussed and tentatively compared to experimental AC losses database conducted at CEA. The outcomes will be discussed and the subsequent guidelines for future work presented.

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JT-60SA superconducting magnet system

Cited by 30 publications

References 16 publications

Recent progress of the JT-60SA project

Recent progress of the JT-60SA project

Progress of JT-60SA Project: EU-JA joint efforts for assembly and fabrication of superconducting tokamak facilities and its research planning

Extensive Analyses of Superconducting Cables 3D Geometry With Advanced Tomographic Examinations

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