Published May 2021 | Version v1
Journal article

Shunt and Rogowski coil measurements on ASDEX Upgrade in support of DEMO detachment control

  • 1. Max Planck Institute for Plasma Physics, 85748 Garching (Germany)
  • 2. Jožef Stefan Institute, Jamova 39, SI-1000 Ljubljana (Slovenia)
  • 3. ITER Organization, Route de Vinon, F-13115 St Paul lez Durance (France)

Description

Highlights: • Aim to develop designs for performing thermo-current measurements in DEMO. • Experiments with shunts and Rogowski coils were performed in AS-DEX Upgrade. • Rogowski coil measurements require stray field compensation of poloidal and toroidal field coil currents. • Shunt measurements with a signal level of 0.75 mV can provide a useful feedback control signal. Detachment control in DEMO is a fundamental requirement to prevent damage to the plasma facing components. Thermo-currents flowing through the plasma facing components of the divertor cassette are driven by the thermoelectric voltage generated by the plasma temperature difference between the inner and outer target plates. Shunt and Rogowski coil measurements to measure thermo-currents for detachment control on ITER are planned. Thermo-current measurements on ASDEX Upgrade have been carried out in support of establishing designs considered suitable to measure thermo-currents in DEMO.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2021.112276

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2021.112276;
PII
S0920379621000521;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
166
Journal Page Range
vp.
ISSN
0920-3796
CODEN
FEDEEE

Optional Information

Copyright
Copyright (c) 2021 Elsevier B.V. All rights reserved.
Collaborations
ASDEX Upgrade team (see the author list of H. Meyer et al. 2019 Nucl. Fusion 59 112014)