Fusion and Plasma Physics
The fusion process encompasses light elements, such as hydrogen and its isotopes deuterium and tritium, to merge to heavier elements, such as helium, thereby releasing large amounts of energy in form of MeV neutrons and protons. To harness this energy, a plasma needs to confined either magnetically or inertially, and heated to temperatures in excess of 100 million Kelvins. At these temperatures the fusion process becomes self-sustained by heating of the plasma via energetic by-products, such as helium. The fusion challenge consists in confining the plasma sufficiently long and controlling its interaction with the surrounding walls.
The group’s research activities concentrate on the tokamak concept. We participate in experiments at present fusion facilities, such as ASDEX Upgrade, DIII-D, and JET, develop and validate computational models for present and future, burning-plasma reactors, such as ITER, and develop diagnostics for fusion relevant experiments.
The group is part of FinnFusion, the domestic agency administrating fusion research within EUROfusion, and member of FuseNet, the European Fusion Education Network facilitating student exchange at Bachelor's, Master's and PhD level. The group is supported by the Academy of Finland and other funding agencies.
Group leader
Mathias Groth
Research
The main research interests are listed below, including codes, experimental apparatuses and facilities, and major scientific results.
Codes used and developed by the Fusion and Plasma Physics group
- Particle orbit simulations: ASCOT
- Plasma turbulence: ELMFIRE
- Scrape-off layer and plasma-wall interaction
Experimental plasma-wall interaction research
Collaboration with experimental research institutes
Open positions
Unfortunately, we currently do not have open positions.
Latest publications
DIII-D research to provide solutions for ITER and fusion energy
Overview of T and D-T results in JET with ITER-like wall
Modeling of plasma facing component erosion, impurity migration, dust transport and melting processes at JET-ILW
Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components
Helium plasma operations on ASDEX Upgrade and JET in support of the non-nuclear phases of ITER
Calibration improvements expand filterscope diagnostic use
Numerical study of limits of neoclassical theory in the plateau regime in the presence of impurities
Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO
Validated edge and core predictions of tungsten erosion and transport in JET ELMy H-mode plasmas
He II line intensity measurements in the JET tokamak
Research group members
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