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MT29 Abstracts and Technical Program

1–6 Jul 2025
Omni Boston Hotel at the Seaport
US/Eastern timezone

Conference Management

Session

Wed-Af-Po.11 - Modelling of Fusion Conductors and Coils I

2 Jul 2025, 14:30
Ensemble Ballroom, Level 2

Ensemble Ballroom, Level 2

Conveners

Wed-Af-Po.11 - Modelling of Fusion Conductors and Coils I

  • Juan Bascunan (Massachusetts Institute of Technology)
  • Hongyu Bai (National High Magnetic Fied Laboratory)

Presentation materials

There are no materials yet.

  1. 279. Wed-Af-Po.11-01: Development of a thermal-hydraulic simulation module for cable stability analysis
    Ms Renjie Huang (Institute of Electrical Engineering, Chinese Academy of Sciences)
    02/07/2025, 14:30
    Poster

    In this paper, we develop a new thermal-hydraulic simulation module as part of the Tokamak magnet software under development. The module focuses on the coupling effect between thermo-hydraulics and electromagnetism to study the LTS/HTS cable-in-conduit-conductor (CICC) stability margin and quench characteristics. The algorithm of the program is based on the finite element method. We present...

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  2. 465. Wed-Af-Po.11-02: Multiphysics verification and validation of STEP toroidal field cable and remountable joints
    Sam Tippetts (UKAEA)
    02/07/2025, 14:30
    Poster

    The Spherical Tokamak for Energy Production (STEP) is a prototype fusion power plant, planned to be operational in the 2040s. The STEP concept depends for its continuous operation on a system of high-temperature superconducting (HTS) magnets. The Toroidal Field (TF) magnets are required to be re-mountable, allowing for the vertical maintenance strategy adopted by the STEP programme. Verified...

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  3. 588. Wed-Af-Po.11-03: Impact of axial and bending strain on the Tcs of ITER TF conductors under MTCB working conditions
    Lorenzo Cavallucci
    02/07/2025, 14:30
    Poster

    The ITER Toroidal Field (TF) coils are manufactured in the double-pancake configuration with cable-in-conduit-conductors (CICC), each containing several hundreds of Nb3Sn strands. These strands are produced by eight different companies using either the bronze-route or the internal-tin manufacturing process. These differences in the manufacturing procedure result in different performances of...

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  4. 444. Wed-Af-Po.11-04: Modelling Current Distribution and Transport Losses in High-Temperature Superconducting Toroidal Field Coils for Fusion Applications
    Mr Oriol Fernández Serracanta (University of Strathclyde)
    02/07/2025, 14:30
    Poster

    The transition from low-temperature superconductors (LTS) to high-temperature superconductors (HTS) has opened new possibilities for toroidal field coil design in fusion applications. These next-generation HTS coils represent a significant departure from traditional D-shaped LTS coils, introducing unique operational dynamics and challenges. A key innovation is the adoption of HTS stacks, where...

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  5. 198. Wed-Af-Po.11-05: AC losses of scaled HTS TF magnets under various magnetic fields
    Yuyang Wu (University of Cambridge)
    02/07/2025, 14:30
    Poster

    High-temperature superconductor (HTS) magnets are gaining attention for their vital position of compact, high-field tokamaks, helping speed up the path to fusion energy. In future commercial nuclear fusion plants, steady-state operations lasting several months will be required. One of the main challenges for steady-state operation is the instability of plasma confinement, which can be reduced...

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  6. 880. Wed-Af-Po.11-06: Thermal hydraulic simulation of Tcs test in the ITER Magnet Cold test facility
    Mr Junjun Li
    02/07/2025, 14:30
    Poster

    The Magnet Cold Test Bench (MCTB) will be assembled and commissioned in 2025 with existing ITER systems (Cold terminal Box, Cryogenic system,) and new components (cryostat, power supply, interconnection valve box). The objective is to test as many TF coils as possible in the MCTB without impacting the assembly schedule in the pit. ITER TF magnet system consist of 18 coils. The Current sharing...

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  7. 640. Wed-Af-Po.11-07: Residual Inductive Voltage Calculations for the Quench Detection Loops of the ITER TF Coils during Single Coil Testing in the ITER Magnet Cold Test Bench
    Thierry Schild (ITER)
    02/07/2025, 14:30
    Poster

    While the ITER assembly is progressing, a Magnet Cold Test Bench (MCTB) is also under preparation to test some of the ITER superconducting coils at 4 K up to nominal current before their installation in the pit. In this context calculations were performed to estimate the residual inductive voltages in the quench detection loops of the TF coils during the test scenarios. These residual...

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  8. 354. Wed-Af-Po.11-08: Calculating the expected critical current for 3D coils of arbitrary shape made with VIPER-like HTS cable
    Robert S Granetz (MIT Plasma Science and Fusion Center)
    02/07/2025, 14:30
    Poster

    Superconducting coils utilizing VIPER-like HTS cable for tokamaks and
    stellarators are being designed, built, and tested. In order to assess a coil's ability to operate at the desired current, and/or to evaluate
    possible degradation of a coil's performance due to manufacturing
    processes, it is necessary to calculate the expected critical current, Ic, of the coil. This is actually a...

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