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Section: Application Domains
Magnetic confinment fusion
The main application domain is magnetic confined fusion. A part of the work is actually used on european Tokamaks like JET, WEST and ITER.
Overall Objectives
Research Program
Application Domains
Highlights of the Year
New Results
- Mathematical theory of reduced MHD models
- 2D
C 1 - Simulations of hydraulic jumps with a turbulent Shallow Water model
- Block-structured meshes
- FEM-BEM coupling methods for Tokamak plasma axisymmetric free-boundary equilibrium computations in unbounded domains
- Optimal control of a coupled partial and ordinary differential equations system for the assimilation of polarimetry Stokes vector measurements in tokamak free-boundary equilibrium reconstruction with application to ITER
- Equilibrium reconstruction with Equinox at JET
- Equilibrium reconstruction within the framework of the European Integrated Tokamak Modelling WPCD project
- Coupling free boundary equilibrium code and magnetic controller on IMAS
- An Automated Approach to Plasma Breakdown Design
- A high order method for the approximation of integrals over simplicity defined hypersurfaces
- FEMs on Composite Meshes for Tuning Plasma Equilibria in Tokamaks
- Automating the design of tokamak experiment scenarios
- Higher order FEM for Free-Boundary Equilibrium in FEEQS
- The two temperature MHD model
- Spectral element schemes for dispersive equations
- Cubature nodes for spectral element methods on symplicial meshes
- Validation of the Full MHD with Bohm Boundary conditions
- Non-linear MHD simulations of QH-mode DIII-D plasmas : ITER high Q scenarios
- Sharpening diffuse interfaces with compressible fluids on unstructured meshes
Partnerships and Cooperations
Bibliography