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Structural optimisation of the DEMO alternative divertor configurations based on FE and RBF mesh morphing
Andrea Chiappa1, Christian Bachmann2, Francesco Maviglia2
1RBF Morph Srl, Via Rosmini 4, Montecompatri 00040 Rome, Italy.
Heliyon
|March 10, 2023
Summary
This study optimized toroidal field coil shapes for advanced divertor configurations in fusion reactors. The new designs significantly reduce stress levels, improving structural integrity for future fusion energy devices.
Area of Science:
- Nuclear Fusion Engineering
- Plasma Physics
- Structural Mechanics
Background:
- Tokamak design, like for the DEMO fusion reactor, is complex due to multidisciplinary physics and engineering requirements.
- Toroidal field (TF) coils are critical for plasma confinement and must withstand significant electromagnetic forces.
- Advanced divertor configurations (ADCs) necessitate TF coil shape adaptations due to larger structural requirements.
Purpose of the Study:
- To adapt the shape of toroidal field coils for advanced divertor configurations in the DEMO tokamak.
- To investigate structural optimization strategies for TF coils under demanding operational loads.
- To reduce the high static membrane stress levels in TF coils.
Main Methods:
- A structural optimization procedure was applied to the reference TF coil shape.
- The strategy involved achieving an iso-stress profile for each coil.
- Radial basis functions mesh morphing was used to transform the baseline finite element model.
Main Results:
- Candidate TF coil shapes were determined for each advanced divertor configuration case.
- Static membrane stress levels during magnetization were significantly reduced from over 700 MPa to below 450 MPa.
- The optimized shapes facilitate the integration of larger divertor structures within the TF coils.
Conclusions:
- The applied structural optimization strategy successfully adapted TF coil shapes for ADCs.
- The optimized designs offer improved structural performance by reducing stress concentrations.
- This approach provides a pathway for designing robust TF coils for future fusion reactors.
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