Validation of TOKES vapor shield simulations against experiments in the 2MK-200 facility

• Published in: Fusion engineering and design Vol. 124; pp. 401 - 404
• Main Authors: Pestchanyi, S., Pitts, R.A., Safronov, V.
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01.11.2017; Elsevier Science Ltd
• Subjects: Computer simulation; Diffusion; Electron density; Electron density profiles; Electron energy; Experimental code validation; Heat; Heat flux; Numeric simulations; Plasma; Plasma shield; Plasma temperature; Radiation; Temperature profiles; Time dependence; TOKES; Tungsten; Plasma shield; Experimental code validation; TOKES; Numeric simulations
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2017.02.048

•Validations of TOKES code simulations for the plasma shield in ITER during disruptions have been performed.•For this purpose measurements of tungsten plasma shield dynamics have been performed in the 2MK-200 facility under ITER relevant conditions.•The experimental and simulated results are in a good agreement. Measurements of tungsten (W) plasma shield dynamics have been performed in the 2MK-200 facility under ITER relevant disruptive plasma heat flux densities of ∼100GW/m2. Plasma temperature profiles at two time instants and time dependent electron density profiles are available from these experiments. These data have been used to validate TOKES code simulations of the W plasma shield which is computed to form in front of the ITER W divertor targets during disruptions. The experimental and simulated temperature profiles are in a good agreement for the measurement points at distances of 1–5cm from the target. An important feature of the W plasma shield seen in the code simulations is the sharp electron temperature drop very close to the target. This region is not resolved in the 2MK-200 facility because of unacceptably low signal/noise ratio. Further experiments in a new, larger plasma gun are planned for experimental validation of this feature.