This paper presents a novel method for accurately tracing magnetic field lines. This procedure is of particular interest for axisymmetric nuclear fusion devices. The design of the plasma facing components in a tokamak strictly depends on the Scrape-Off Layer (SOL), a thin region of open field lines through which charged particles and energy flow out from the plasma core to the solid walls with a huge heat flux. The power exhaust issue is among the top priorities in the European Fusion Roadmap, hence the determination of the plasma boundary and SOL with a high accuracy is essential. Existing equilibrium codes using finite element formulations with linear triangles of mesh size h provide a piecewise constant magnetic flux gradient, resulting in coarse accuracy of the field lines in the SOL, with an error of order O(h), especially near the X-point where the flux gradient approaches zero. The proposed procedure is based on a method introduced in 2023, which achieves continuity and a convergence rate of order O(h^2) for the magnetic flux gradient too. The magnetic poloidal flux is then approximated with a piecewise polynomial function of second or third degree in the triangles. A more accurate evaluation of the plasma boundary and SOL field lines is obtained, particularly near the X-point, which is no longer constrained to be a mesh node. The method has been successfully tested in two cases with available analytical solutions. It has also been used as a post-processor for the flat top configuration of the DTT tokamak obtained with the free boundary CREATE-NL+ equilibrium code. For a given accuracy, the computational cost of the procedure is significantly lower than alternative methods relying on finer first order discretization or techniques using triangular C1 finite elements.
Accurate plasma boundary calculation using linear triangular finite elements
Neri, Marco;Zumbolo, Pasquale
;
2025
Abstract
This paper presents a novel method for accurately tracing magnetic field lines. This procedure is of particular interest for axisymmetric nuclear fusion devices. The design of the plasma facing components in a tokamak strictly depends on the Scrape-Off Layer (SOL), a thin region of open field lines through which charged particles and energy flow out from the plasma core to the solid walls with a huge heat flux. The power exhaust issue is among the top priorities in the European Fusion Roadmap, hence the determination of the plasma boundary and SOL with a high accuracy is essential. Existing equilibrium codes using finite element formulations with linear triangles of mesh size h provide a piecewise constant magnetic flux gradient, resulting in coarse accuracy of the field lines in the SOL, with an error of order O(h), especially near the X-point where the flux gradient approaches zero. The proposed procedure is based on a method introduced in 2023, which achieves continuity and a convergence rate of order O(h^2) for the magnetic flux gradient too. The magnetic poloidal flux is then approximated with a piecewise polynomial function of second or third degree in the triangles. A more accurate evaluation of the plasma boundary and SOL field lines is obtained, particularly near the X-point, which is no longer constrained to be a mesh node. The method has been successfully tested in two cases with available analytical solutions. It has also been used as a post-processor for the flat top configuration of the DTT tokamak obtained with the free boundary CREATE-NL+ equilibrium code. For a given accuracy, the computational cost of the procedure is significantly lower than alternative methods relying on finer first order discretization or techniques using triangular C1 finite elements.Pubblicazioni consigliate
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