Progress in the design of the superconducting magnets for the EU DEMO

V Corato, T Bagni, ME Biancolini, R Bonifetto… - Fusion engineering and …, 2018 - Elsevier
In the framework of the DEMOnstration fusion power plant (DEMO) design coordinated by
the EUROfusion consortium, a pre-conceptual design of the superconducting magnet …

Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors

X Liu, F Wu, Z Wang, G Li, X Liu, H Li, J Li, Y Ren… - Nuclear …, 2020 - iopscience.iop.org
A comprehensive research facility project was approved in December 2018 with funding of
345 million EUR, to support the research and development of the China Fusion Engineering …

DC test results of the DEMO TF React&Wind conductor prototype no. 2

K Sedlak, P Bruzzone, B Stepanov… - IEEE Transactions …, 2019 - ieeexplore.ieee.org
In 2013, the EUROfusion organization launched the preconceptual design studies of the
fusion DEMO tokamak. Several options of superconducting magnet design are investigated …

An approach of calculating winding pack smeared properties for TF magnets using artificial neural network

F Wu, X Liu, X Gao, J Zhang, D Wang, J Zhu… - Fusion Engineering and …, 2023 - Elsevier
Tokamak superconducting TF coils experience severe structural and thermal loads during
operation. Hence optimizing the design of the conductor and the coil is crucial, making it …

A methodological approach for the optimal design of the toroidal field coils of a tokamak device using artificial intelligence

G Tomassetti, G de Marzi, CF Zignani… - Superconductor …, 2021 - iopscience.iop.org
As prototypes of future commercial tokamaks, DEMOs nuclear fusion power plants are
expected to be able to produce cost-effective electrical power. In this view, an optimized …

An analytical thermal model for the optimization of EU DEMO feeder thermal shields

C Groth, A Chiappa, R Guarino - Fusion Engineering and Design, 2024 - Elsevier
The present work aims at defining a first design of the DEMO EU's feeder thermal shield for
the CFT, by exploring the temperature distribution resulting from radiation and conduction …

Time-extended inductive tokamak discharges with differentially-tilted toroidal field coils

R Gatto, F Bombarda, S Gabriellini, S Murgo… - Nuclear …, 2023 - iopscience.iop.org
The strong toroidal magnetic field required for plasma confinement in tokamaks is generated
by a set of D-shaped coils lying equidistant on meridian planes toroidally located around the …

Crack propagation analysis of ITER Vacuum Vessel port stub with Radial Basis Functions mesh morphing

E Pompa, G D'Amico, S Porziani, F Giorgetti… - Fusion Engineering and …, 2020 - Elsevier
Abstract The ITER Vacuum Vessel (VV) is one of the most important components of the
tokamak machine. The severe operating conditions impose a design to withstand strong …

Identification of the postulated initiating events of accidents occurring in a toroidal field magnet of the EU DEMO

R Bonifetto, N Pedroni, L Savoldi… - Fusion Science and …, 2019 - Taylor & Francis
The design of the European Union (EU) DEMO reactor magnet system, currently ongoing
within the EUROfusion consortium, will take advantage of the know-how developed during …

Structural assessment of TF superconducting magnet of the DTT device

A Chiappa, A Di Zenobio, F Giorgetti, C Groth… - Procedia Structural …, 2019 - Elsevier
The paper presents the multi-physics study of the Toroidal Field (TF) coils of the DTT device,
as defined according to the design of the “Divertor Tokamak Test facility Interim Design …