Interpretative modelling of boron transport in the WEST boundary plasma in experiments with impurity powder dropper
POSTER
Abstract
One of the goals of the WEST tokamak is to test the viability of W plasma-facing components (PFCs) in a tokamak environment in order to prepare operation for future devices like ITER and DEMO. Usage of W PFCs leads to the contamination of the core plasma by W, which can cause significant radiative energy loss. A common technique to prevent W contamination of tokamak plasma is conditioning of PFCs with low-Z coating layers. Active wall conditioning is being studied in WEST through the injection of B powder with a PPPL Impurity Powder Dropper (IPD). An open question in this process is the nature of the transport and deposition of the B atoms on PFCs. For this reason, a modelling workflow is developed to analyze the impact of B injection on the plasma and to interpret experimental data. The workflow consists of a) deuterium-oxygen (D+O) plasma modelling to simulate plasma prior to B injection; b) B powder ablation modelling using the Dust Injection Simulator (DIS) code; and c) D+O+B plasma modelling with B neutral source provided by dust ablation modelling. Synthetic diagnostic tools are applied to measure the impact of B injection on plasma parameters in the simulation and the results are compared with the measurements by various diagnostics during IPD experiments in WEST.
*This work is funded by French Alternative Energies and Atomic Energy Commission.This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 — EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor the European Commission can be held responsible for them.
Presenters
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Kirill Afonin
- CEA Cadarache