Fusion reactor development. Particular project: Plasma-wall interactions in fusion devices
Project description
Design and construction of a next step controlled fusion device (ITER) is preceded by development, selection and characterization of materials relevant for plasma-facing components– especially for the first wall and the divertor. Tungsten and beryllium were selected for ITER; results obtained also by the KTH group influenced that choice.
Material erosion, transport and re-deposition leading to the fuel accumulation in wall materials top the list of urgent priority issues to be assessed in present-day devices to provide the best possible predictions for a reactor. Experimental work is carried out at Joint European Torus (JET), ASDEX Upgrade, and WEST, and also in linear simulators of plasma-surface interactions. Materials are examined using a large number of material research techniques.
Year
Team
KTH Royal Institute of Technology, School of Electrical Engineering and Computer Science, Department of Fusion Plasma Physics
- Marek Rubel, Team leader, professor
- Per Brunsell, professor
- Per Petersson, researcher
- Henric Bergsåker, associate professor
- Laura Dittrich, student
Uppsala University, Department of Physics
- Daniel Primetzhofer, professor
Core deliverables
- Testing of beryllium and tungsten behaviour under plasma operation
- Determination of the impact of material migration and mixing on the wall composition and retention of hydrogen isotopes
- Mechanism of dust generation and detailed characterisation of particles
- Mechanism and efficiency of fuel removal and wall conditions under ion cyclotron-assisted plasma operation
- Development of diagnostic tools and the determination of the plasma impact on diagnostic components
Total budget
Collaborations
- KTH Royal Institute of Technology
- Uppsala University
- EURO-fusion Consotrium
- Culham Centre for Fusion Energy, Joint European Torus (JET), UK
- Forschungszentrum Juelich, Germany
- Warsaw University of Technology, Poland
Hyperlink
