70 likes | 270 Views
Plans for magnetic perturbation experiments on the COMPASS tokamak. Pavel Cahyna, Radomír Pánek Institute of Plasma Physics AS CR v.v.i., Association EURATOM/IPP.CR, Prague, Czech Rep. The COMPASS tokamak – features. Smallest tokamak (R=0.56 m) with H-mode and ITER-relevant geometry
E N D
Plans for magnetic perturbation experiments on the COMPASS tokamak Pavel Cahyna, Radomír Pánek Institute of Plasma Physics AS CR v.v.i., Association EURATOM/IPP.CR, Prague, Czech Rep.
The COMPASS tokamak – features • Smallest tokamak (R=0.56 m) with H-mode and ITER-relevant geometry • Experimental program focused on pedestal physics, L-H transition, edge plasma • Rich magnetic diagnostic • NBI both balanced and co-injection • “Saddle coils” to create magnetic perturbations
COMPASS saddle coils • A set of coils segments, independently connectable, for producing magnetic perturbations • Toroidal symmetry n=2 • Off-midplane and on-midplane coils • Installation of new n=4 set of coils planned
On-midplane Off-midplane Selected coil configurations • Both configurations can be combined into a 3-row configuration. • Maximum current in the coil segments is about 4 kA.
COMPASS - near future plans • Performance • Ohmic H-mode 1/10 • NBI (2 x, balanced or co-injection) 8/10 • Perturbation coils • Present configuration (n=2) 3/10 • Upgrade (n=4) 7/10
COMPASS diagnostics • Diagnostics existing or being installed • HR Thomson (2mm 60 Hz edge resolution) 6/10 • Edge reflectometry (μs resolution density measurement) 6/10 • Probes (fixed + 2 reciprocating) 1/10 • Li beam 12/09 • 2x fast visible camera 12/09 • Edge rotation measurement 3/10 • Atomic beam probe (edge current measurement) 6/10 • Divertor Langmuir probes 1 row - 36 probes present • Under consideration • Heavy ion beam probe (for plasma potential profile measurements) • IR cameras (divertor region) • CXRS on the heating beam for toroidal rotation measurements
Possible contributions to the ITPA work plan • Comparison of midplane vs. off-midplane coils • Comparison of different toroidal mode numbers (requires n=4 coil set) • Quantification of the impact on pedestal height • Attempt to get an effect on type-I ELMs (if type-I ELM regime obtained – in NBI heated plasma) • Observe divertor power loads (divertor footprints – requires IR camera) • Impact on toroidal velocity (requires CXRS) • Verification of models • Joint experiments