TY - GEN
T1 - ASDEX upgrade results and future plans
AU - Kallenbach, A.
AU - Bobkov, V.
AU - Braun, F.
AU - Herrmann, A.
AU - Höhnle, H.
AU - McDermott, R. M.
AU - Neu, R.
AU - Noterdaeme, J. M.
AU - Pütterich, T.
AU - Schweinzer, J.
AU - Stober, J.
AU - Strumberger, E.
AU - Suttrop, W.
AU - Wagner, D.
AU - Zohm, H.
PY - 2011
Y1 - 2011
N2 - ASDEX Upgrade is an ITER shaped divertor tokamak with versatile heating, fueling, exhaust and control systems. All plasma facing components are coated with tungsten layers. Plasma scenarios have been adopted to avoid central tungsten accumulation, which can lead to an H-L transition due to excessive central radiative losses. Compared to a carbon-PFC tokamak, the AUG operation space is slightly more weighted towards higher densities and collisionalities. Actual and future planned extensions aim towards reducing the core collisionality while maintaining good power and particle exhaust. These extensions include a solid tungsten outer divertor target, improved pumping, a higher ECRH power and modified ICRF antennas for reduced tungsten sources. The newest element for advanced plasma control is the first set of 8 magnetic perturbation coils, which already achieved type-I ELM mitigation in various plasma scenarios. Another 8 coils will be installed in autumn 2011 allowing to produce mode spectra with n > 2. In parallel to the improved actuator set, an increasing number of diagnostics is brought into real-time state, allowing versatile profile and stability control.
AB - ASDEX Upgrade is an ITER shaped divertor tokamak with versatile heating, fueling, exhaust and control systems. All plasma facing components are coated with tungsten layers. Plasma scenarios have been adopted to avoid central tungsten accumulation, which can lead to an H-L transition due to excessive central radiative losses. Compared to a carbon-PFC tokamak, the AUG operation space is slightly more weighted towards higher densities and collisionalities. Actual and future planned extensions aim towards reducing the core collisionality while maintaining good power and particle exhaust. These extensions include a solid tungsten outer divertor target, improved pumping, a higher ECRH power and modified ICRF antennas for reduced tungsten sources. The newest element for advanced plasma control is the first set of 8 magnetic perturbation coils, which already achieved type-I ELM mitigation in various plasma scenarios. Another 8 coils will be installed in autumn 2011 allowing to produce mode spectra with n > 2. In parallel to the improved actuator set, an increasing number of diagnostics is brought into real-time state, allowing versatile profile and stability control.
UR - http://www.scopus.com/inward/record.url?scp=80955141206&partnerID=8YFLogxK
U2 - 10.1109/SOFE.2011.6052356
DO - 10.1109/SOFE.2011.6052356
M3 - Conference contribution
AN - SCOPUS:80955141206
SN - 9781457706691
T3 - Proceedings - Symposium on Fusion Engineering
BT - 2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011
T2 - 2011 IEEE/NPSS 24th Symposium on Fusion Engineering, SOFE 2011
Y2 - 26 June 2011 through 30 June 2011
ER -