29th Symposium on Fusion Technology (SOFT 2016)

Session

O5C

Sep 8, 2016, 4:40 PM

Prague Congress Centre

49544. O5C.1 First Operational Phase of the Superconducting Magnet System of Wendelstein 7-X

Konrad Risse (W7-X Operation)

9/8/16, 4:40 PM

E. Magnets and Power Supplies

Oral

The Wendelstein 7-X stellarator (W7-X), one of the largest stellarator fusion experiments, is presently in the first operational phase at the Max Planck Institute for Plasma Physics in Greifswald, Germany. The W7-X shall prove the reactor relevance of the optimized stellarator concept. To confine 30m³3 plasma the W7-X machine has a superconducting magnet system with 50 non-planar...

49545. O5C.2 Development and Commissioning of the Wendelstein 7-X Safety Control System

Andreas Werner (Wendelstein 7-X Operation CoDaC)

9/8/16, 5:00 PM

C. Plasma Engineering and Control

Oral

The Wendelstein 7-X safety control system is one of the main central control entities and ensures personal safety and investment protection. Its proper definition and setup has been a major precondition for the operation permit by the authorities and was inspected by external reviewers several times. The safety control systems has a distributed architecture comprising of the central safety...

49546. O5C.3 An optimized upper divertor with divertor-coils to study enhanced divertor configurations in ASDEX Upgrade

Albrecht Herrmann (MPI für Plasmaphysik)

9/8/16, 5:20 PM

C. Plasma Engineering and Control

Oral

ASDEX Upgrade came into operation in 1991. It was designed as a tokamak with reactor relevant shaping. The coil and control system allows to operate in lower single null (LSN), double null (DN) or upper single null (USN) with up to 1.6 MA plasma current and an initially open divertor configuration. Divertor enhancements were concentrated on the lower divertor that was finally transferred to a...

49547. O5C.4 Optimal current profile control for enhanced repeatability of L-mode and H-mode discharges in DIII-D

William Wehner (Mechanical Engineering & Mechanics)

9/8/16, 5:40 PM

C. Plasma Engineering and Control

Oral

To collect meaningful experimental data, it is necessary to maintain consistent operating conditions in the tokamak plasma across repeated discharges. Presently, the desired plasma formation conditions, such as the shape of the plasma current profile, are achieved in a trial and error fashion, which can be a lengthy, wasteful process. In this work, model-based control techniques including...