Error field and correction coils in DTT: A preliminary analysis

R Albanese, T Bolzonella, AG Chiariello… - Fusion Engineering and …, 2023 - Elsevier
Abstract The Divertor Tokamak Test (DTT) facility, construction starting at Frascati, Italy, is
designed to test different solutions for divertor in view of DEMO. A preliminary analysis of the …

Divertor Tokamak Test facility Project: Status of Design and Implementation

F Romanelli - Nuclear Fusion, 2024 - iopscience.iop.org
An overview is presented of the progress since 2021 in the construction and scientific
programme preparation of the Divertor Tokamak Test (DTT) facility. Licensing for building …

DTT: A challenging framework for a sound superconducting magnets design

A Di Zenobio, A Anemona, R Bonifetto… - IEEE Transactions …, 2022 - ieeexplore.ieee.org
At the ENEA's research center of Frascati, the DTT (Divertor Tokamak Test) facility is
currently under construction. The activity of this experimental nuclear fusion reactor, will be …

3D-FOX—a 3D transient electromagnetic code for Eddy currents computation in superconducting magnet structures: DTT TF fast current discharge analysis

R Bonifetto, M De Bastiani, R Zanino… - IEEE Access, 2022 - ieeexplore.ieee.org
Bulky metallic structures are needed in the toroidal field (TF) superconducting magnets for
fusion applications to withstand the large Lorentz forces acting on the winding. The pulsed …

Multiphysics model of quench for the ITER Central solenoid

L Cavallucci, F Gauthier, M Breschi… - IEEE Transactions …, 2023 - ieeexplore.ieee.org
The ITER Central Solenoid (CS), the backbone of the ITER magnet system, is composed of 6
modules, each made of 40 pancakes, for a total conductor length of about 36 km. More than …

Modeling of quench in the ITER poloidal field coils

L Cavallucci, A Louzguiti, C Hoa… - IEEE Transactions …, 2024 - ieeexplore.ieee.org
The SuperMagnet suite of code is here applied to study the Poloidal Field (PF) and
Correction Coils (CC) and their cryogenic distribution during a quench in the PF coils. In the …

DTT toroidal field conductor samples test in Sultan: DC and AC characterization

CF Zignani, G De Marzi, G Scarantino… - Superconductor …, 2024 - iopscience.iop.org
The superconducting magnet system of the Divertor Tokamak Test (DTT) facility, composed
of 18 toroidal field (TF) coils, 6 poloidal field coils and a central solenoid, has been designed …

An improved analysis method for assessing the nuclear-heating impact on the stability of toroidal field magnets in fusion reactors

YD Lu, JX Zheng, XF Liu, H Wu, J Ge, K Xu, M Li… - Nuclear Science and …, 2024 - Springer
The superconducting magnet system of a fusion reactor plays a vital role in plasma
confinement, a process that can be disrupted by various operational factors. A critical …

Application of the Polynomial Chaos Expansion to the Uncertainty Propagation in Fault Transients in Nuclear Fusion Reactors: DTT TF Fast Current Discharge

M De Bastiani, A Aimetta, R Bonifetto, S Dulla - Applied Sciences, 2024 - mdpi.com
Nuclear fusion reactors are composed of several complex components whose behavior may
be not certain a priori. This uncertainty may have a significant impact on the evolution of fault …

[HTML][HTML] Electro dynamic model of eddy currents in EU DEMO TF coil casing during major plasma disruption

M De Bastiani, R Bonifetto, G Messina, L Morici… - Fusion Engineering and …, 2023 - Elsevier
The conceptual design of the EU DEMO reactor is currently ongoing within the EUROfusion
consortium. Many different fault transients must be considered and carefully analyzed in the …