Anand, H.Pitts, R. A.De Vries, P. C.Snipes, J. A.Nespoli, F.Labit, B.Galperti, C.Coda, S.Brank, M.Kos, L.2019-10-162019-10-162019-10-162019-10-0110.1016/j.fusengdes.2019.111242https://infoscience.epfl.ch/handle/20.500.14299/162042WOS:000487765500023A 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.Nuclear Science & Technologyreal-time controlheat flux estimation on plasma-facing componentsreal-time equilibrium solverscrape-off layermagnetic field-line tracingplasma-facing componentsplasmadepositiontext::journal::journal article::research article