Published August 2017 | Version v1
Journal article

Detachment evolution on the TCV tokamak

  • 1. CCFE, Culham Science Centre, Abingdon, OX14 3DB, Oxon (United Kingdom)
  • 2. FOM Institute DIFFER, Dutch Institute for Fundamental Energy Research (Netherlands)
  • 3. Ecole Polytechnique Fédérale de Lausanne (EPFL), SPC, 1015 Lausanne (Switzerland)
  • 4. York Plasma Institute, Department of Physics, University of York, Heslington, York, YO10 5DD (United Kingdom)
  • 5. ITER Organization, Route de Vinon-sur-Verdon, St.Paul-lez-Durance, Cedex (France)
  • 6. University of California San Diego (UCSD), San Diego, CA (United States)
  • 7. Max Planck Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany)

Description

Highlights: • A detailed analysis of data from several diagnostics on TCV has been carried out to study divertor detachment in dedicated experiments. • The detachment "front" location has been tracked during the evolution of detachment inferred from tomographically inverted C III and Dα emission. • The analysed data was found to have good overall consistency, which has been verified using OSM-EIRENE-DIVIMP modelling. - Abstract: Divertor detachment in the TCV tokamak has been investigated through experiments and modelling. Density ramp experiments were carried out in ohmic heated L-mode pulses with the ion ∇B drift directed away from the primary X-point, similar to previous studies [1]. Before the roll-over in the ion current to the outer strike point, C III and Dα emission from the outer leg recede slowly from the strike point toward the X-point, at a rate of ∼2.0 × 10−19 m/m−3 along the magnetic field as the electron temperature along the leg reduces with increasing density. Around the onset of detachment, the upstream density profile and outer target Dα profiles broaden, possibly leading to an increase in radiation in the SOL by increased interaction between the SOL and the carbon tiles lining the outer wall. The plasma conditions upstream and at various locations along the detached outer divertor leg have been characterised, and the consistency of this data has been checked with the interpretive OSM-EIRENE-DIVIMP suite of codes [2] and are broadly found to be consistent with measured Dγ/Dα emissivity profiles along the detached outer divertor leg.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nme.2016.10.020

Additional details

Identifiers

DOI
10.1016/j.nme.2016.10.020;
PII
S2352179116302022;

Publishing Information

Journal Title
Nuclear Materials and Energy
Journal Volume
12
Journal Page Range
p. 1071-1076
ISSN
2352-1791

Conference

Title
22. International Conference on Plasma-Surface Interactions in Controlled Fusion Devices
Acronym
PSI-22
Dates
30 May - 3 Jun 2016
Place
Rome (Italy)

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50079896
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AUGMENTATION; DATA ANALYSIS; DENSITY; DIVERTORS; ELECTRON TEMPERATURE; EMISSIVITY; EVOLUTION; LEGS; L-MODE PLASMA CONFINEMENT; MAGNETIC FIELDS; TCV TOKAMAK
Descriptors DEC
BODY; CLOSED PLASMA DEVICES; CONFINEMENT; DATA PROCESSING; LIMBS; MAGNETIC CONFINEMENT; OPTICAL PROPERTIES; PHYSICAL PROPERTIES; PLASMA CONFINEMENT; PROCESSING; SURFACE PROPERTIES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Notes
© 2017 United Kingdom Atomic Energy Authority. Published by Elsevier Ltd.
Collaborations
the MST1 and TCV Teams