Vertical displacement events analysis using MAXFEA code in combination with ANSYS APDL in the final design stage of the DTT vacuum vessel

F Giorgetti, R Lombroni, VG Belardi, G Calabrò… - Fusion Engineering and …, 2022 - Elsevier
In the context of the Divertor Tokamak Test facility (DTT) project, a recently developed
procedure based on the use of MAXFEA code in combination with ANSYS APDL already …

[HTML][HTML] Corrosion of 316L exposed to highly concentrated borated water used as shield in nuclear fusion experimental reactors cooling circuits

C Gasparrini, JO Douglas, A Yazdanpanah, R Stroud… - Corrosion …, 2024 - Elsevier
Borated water is used as a shield in nuclear fusion cooling circuits. General corrosion,
activated corrosion products (ACPs) formation and stress corrosion cracking initiation of 316 …

Water chemistry in fusion cooling systems: borated water for DTT vacuum vessel

C Gasparrini, D Badocco, L Di Pace… - … on Plasma Science, 2022 - ieeexplore.ieee.org
The Divertor Tokamak Test (DTT) vacuum vessel (VV) is a toroidal chamber that ensures an
enclosed vacuum environment for the plasma, a confinement barrier, and temperature …

[HTML][HTML] Use of MAXFEA-ANSYS tool to study the Electro-Magnetic behaviour of the new ST40 inner vacuum chamber proposal during a plasma VDE

R Lombroni, S Carusotti, F Giorgetti, M Scarpari… - Fusion Engineering and …, 2023 - Elsevier
Abstract Tokamak Energy Ltd. is developing compact fusion power plants based on two
promising technologies, Spherical Tokamaks (STs) and High Temperature Superconductors …

Preliminary thermal-hydraulic deterministic safety analysis of an in-vessel LOCA for the DTT facility

G Grippo, A Bersano, F Mascari - Journal of Physics: Conference …, 2024 - iopscience.iop.org
Abstract The DTT (Divertor Tokamak Test) facility is a new experimental tokamak under
development by an Italian consortium in cooperation with several high-standard European …

Reduced Order Modeling for Real-Time Monitoring of Structural Displacements due to Electromagnetic Forces in Large Scale Tokamaks

F Lucchini, A Frescura, R Torchio, P Alotto… - arXiv preprint arXiv …, 2024 - arxiv.org
The real-time monitoring of the structural displacement of the Vacuum Vessel (VV) of
thermonuclear fusion devices caused by electromagnetic (EM) loads is of great interest. In …

Status of design and procurement activities in DTT tokamak project area

GM Polli, A Cucchiaro, M Dalla Palma… - 2022 IEEE 21st …, 2022 - ieeexplore.ieee.org
DTT, Divertor Tokamak Test facility, is one of the largest nuclear fusion facility under
construction in Europe after ITER. Its mission is to provide an integrated nuclear fusion …

[PDF][PDF] Borated water chemistry control for DTT vacuum vessel

M Utili, C Cavallini, M D'Onorio… - … and Materials for …, 2023 - conferences.iaea.org
BORATED WATER CHEMISTRY CONTROL FOR DTT VACUUM VESSEL Page 1 01
November, 2023 BORATED WATER CHEMISTRY CONTROL FOR DTT VACUUM VESSEL …

Estimation of the power dissipation on the casing of DTT toroidal field coil during a fast plasma disruption

L Morici, G Messina, A Di Zenobio, R Bonifetto… - Fusion Engineering and …, 2023 - Elsevier
The aim of this paper is the computation of the power dissipated on the Toroidal Field Coil
(TFC) casing of the Divertor Tokamak Test facility (DTT). The DTT Tokamak will be installed …

[HTML][HTML] White noise characterization and thermo-mechanical analysis of DTT pick-up coils

M Lacquaniti, G Sias, A Fanni, A Pironti… - Fusion Engineering and …, 2023 - Elsevier
Abstract The Divertor Tokamak Test (DTT)[1] is presently in the start-up phase of
construction. Among diagnostics, the magnetic ones are the first components that will have …