MT29 Abstracts and Technical Program

Session

Wed-Af-Po.09 - Magnets for Tokamaks: Design and Analysis

2 Jul 2025, 14:30

Ensemble Ballroom, Level 2

265. Wed-Af-Po.09-01: Startup of a multi-physics simulation platform for fusion magnet design and analyses

Dr Quanyue Liu (Institute of Electrical Engineering, Chinese Academy of Sciences)

02/07/2025, 14:30

Poster

For advancing the development of fully superconducting tokamak magnets and accelerating the progress to the next step in fusion reactor DEMO design, a refined and integrated large-scale superconducting tokamak simulation platform is being developed in China. The aim is to optimize the design and performance of tokamak magnets, improve their efficiency and reliability, solve complex...

583. Wed-Af-Po.09-02: ENABLING the build of large scale HTS magnets for Spherical Tokamaks.

Rod Bateman

02/07/2025, 14:30

Poster

At Tokamak Energy (TE) we have been working on a range of technology blocks and magnet demonstrators to raise the Technical Readiness Level (TRL) of REBCO HTS based magnets for spherical tokamaks (ST). This is a broad programme addressing technologies including coil manufacturing, quench protection, modelling and simulation, HTS irradiation, and other aspects. This talk will demonstrate how...

806. Wed-Af-Po.09-03: Detailed Margin Analysis due to Field Loading of the HTS Toroidal Field Coil of the STEP Tokamak

William Iliffe

02/07/2025, 14:30

Poster

The economic viability of fusion power plants such as UK Industrial Fusion Solutions Spherical Tokamak for Energy Production (STEP) [1] is a function of their size, toroidal field (TF) strength and availability throughout their operating lifetime [2]. This optimisation has led STEP to adopt a compact design featuring TF cables comprising a stack of rare-earth barium copper oxide (REBCO) ...

350. Wed-Af-Po.09-04: Magnet design activities at CEA for EU-DEMO new baseline

Alexandre Torre

02/07/2025, 14:30

Poster

In 2024, a new EU-DEMO baseline was released which changed substantially the constraints on the magnets systems. In particular, the stored energy of the TF system is about half of the former baseline value, which is bound to impact the magnetic loads as well as the coils protection.
After summarizing the main changes in the design inputs, this paper will present the changes implemented in...

418. Wed-Af-Po.09-05: Design and Analysis of BEST PF coils

Xufeng Liu

02/07/2025, 14:30

Poster

The BEST (Burning Plasma Experimental Superconducting Tokamak) is a compact tokamak device under design. The parameters of the device include major radius is 3.6m, minor radius is 1.1m, plasma current is 7MA, and central field strength is 6.15T. The magnet system of the device consists of 12 central solenoid coils (6 high-temperature superconducting coils and 6 low-temperature superconducting...

409. Wed-Af-Po.09-06: A novel method to design the shape of high-temperature superconducting toroidal field coils for spherical tokamaks

Mr Zhengxin Yin (Tsinghua University)

02/07/2025, 14:30

Poster

The spherical tokamak (ST), characterized by its low aspect ratio and compact geometry, necessitates a toroidal filed (TF) coil design that typically adopts a sharper D-shape profile. This design is distinguished by its slender and tall configuration with a reduced radius of curvature, which can result in localized magnetic field and stress concentration on coils. Furthermore, the...

491. Wed-Af-Po.09-07: DTT Poloidal Field Magnet System

Simonetta Turtu

02/07/2025, 14:30

Poster

DTT (Divertor Tokamak Test) is a fusion reactor facility which is being built in the Research Centre of ENEA Frascati, to cope with the technological challenges related to the divertor system in DEMO. The magnetic system includes 18 toroidal field (TF), a central solenoid (CS) composed by 6 modules and 6 poloidal field (PF) coils. These last are solenoids based on Nb3Sn for the 2 more...

584. Wed-Af-Po.09-08: Toward design finalization for the Central Solenoid coil system of the DTT tokamak

Dr Luigi Muzzi

02/07/2025, 14:30

Poster

The design of the Central Solenoid (CS) for the “Divertor Tokamak Test” (DTT) facility has evolved through different options, investigated with the aim to satisfy the demanding magnetic flux performance required by the DTT scientific program, while providing a robust solution from the manufacturing and operational point of view.
In the present paper we illustrate the current design choice,...

302. Wed-Af-Po.09-09: Suprafusion demonstrator: preliminary conceptual design

Clement Lorin

02/07/2025, 14:30

Poster

The "SupraFusion" program is a French initiative dedicated to advancing High-Temperature Superconductor (HTS) technology. HTS materials enable ultra-high magnetic fields (>20 T) at low temperatures (4 K - 20 K), potentially revolutionizing fields such as fusion energy, wind power, and medical imaging. The program's primary goal is to establish France as a leader in HTS research and innovation,...