Structural Assessment of the DTT Poloidal Field Coil System

In the context of the European fusion roadmap, the divertor tokamak test (DTT) experimental reactor is intended to investigate alternative divertor configurations in view of the EU-DEMO power exhaust handling necessities. The six poloidal field coils of this tokamak are responsible for the plasma sh...

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Bibliographic Details
Published inIEEE transactions on applied superconductivity Vol. 30; no. 4; pp. 1 - 5
Main Authors Zoboli, Lorenzo, Anemona, Alessandro, Zenobio, Aldo Di, Giannini, Lorenzo, Muzzi, Luigi, Righetti, Riccardo, Romanelli, Gherardo, Turtu, Simonetta, Vairo, Giuseppe, Corte, Antonio della
Format Journal Article
LanguageEnglish
Published New York IEEE 01.06.2020
The Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subjects
Divertor tokamak test
Fatigue
FEM analysis
Field coils
Finite element analysis
Finite element method
Insulation
poloidal field coil
Stress
Superconducting magnets
Tokamak devices
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Summary:In the context of the European fusion roadmap, the divertor tokamak test (DTT) experimental reactor is intended to investigate alternative divertor configurations in view of the EU-DEMO power exhaust handling necessities. The six poloidal field coils of this tokamak are responsible for the plasma shape and equilibrium, and numerous steps were taken to obtain a design that is magnetically consistent with plasma requirements and structurally compliant with the chosen failure criterion. This work presents the structural assessment that has been performed on the poloidal coil system, taking into account the cooldown process, the energisation to operating conditions and fatigue. Finite Element Analysis has been employed as the principal means of investigation.
ISSN:1051-8223
1558-2515
DOI:10.1109/TASC.2019.2961894