Experimental implementation of a real-time power flux estimator for the ITER first wall on the TCV tokamak

A control-oriented approach to the monitoring of wall power flux densities on ITER has been successfully developed. It is based on real-time equilibrium reconstruction in 2-D which is then used to describe the deposited heat flux as a poloidal flux function with user specified parameters for the power exhausted into the scrape-off layer (SOL) and the SOL heat flux width. To account for the real 3-D geometry of the plasma-facing components (PFC), appropriate weighting factors are derived from magnetic field line tracing in 3-D. Integration of the 3-D effect is performed with a new GUI-based software environment, SMITER, incorporating a field line tracer and permitting import and meshing of PFC CAD models. The paper discusses the experimental demonstration of the model-based wall heat flux algorithm on the TCV tokamak, reporting on the benchmarking of the new code package, SMITER against infra-red camera heat flux measurements and the derivation of the component shaping weighting factors. A comparison of the real-time estimation of the peak power flux and its spatial location against the off-line infra-red measurement for limiter plasma configurations is presented.

H. Anand, R.A. Pitts, P.C. de Vries, J.A. Snipes, F. Nespoli, et al.. Experimental implementation of a real-time power flux estimator for the ITER first wall on the TCV tokamak. Fusion Engineering and Design, Elsevier, 2019, 147, pp.111242. ⟨10.1016/j.fusengdes.2019.111242⟩. ⟨hal-02468015⟩

Journal: Fusion Engineering and Design

Date de publication: 01-10-2019

Auteurs:
  • H. Anand
  • R.A. Pitts
  • P.C. de Vries
  • J.A. Snipes
  • F. Nespoli
  • B. Labit
  • C. Galperti
  • S. Coda
  • M. Brank
  • L. Kos

Digital object identifier (doi): http://dx.doi.org/10.1016/j.fusengdes.2019.111242

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