Outline:
Heat shields based on solid materials revealed its nuclear and heat flux limits, likely exceeding the requirements of the (near) future high magnetic field and high heating power tokamak reactors like COMPASS Upgrade, ITER and DEMO. This project therefore investigates tokamak scrape-off layer (SOL) plasma interactions with a (potential replacement of current technologies) liquid metal divertor (LMD) [1, 2, 3] as well as with contemporary tungsten heat shields (already assumed as the only well-enough known option).
The PhD student will implement a three-dimensional Monte Carlo code ERO [4] (or WallDYN, and/or CoreDIV [5]), used usually for graphite and tungsten sputtering, through which he will mainly simulate Li and Sn deposition on tokamaks wall when released from LMD.
During this PhD project, the student is expected to
- stay at least 1⁄2 year at Ghent University or in a laboratory designated by the university
- publish at least 2 first-author papers and co-author many other papers
- attend at least 2 international conferences and at least 2 doctoral student conferences
- keep long-term fruitful scientific contact
References:
[1] J. Horacek, et. al.: Predictive modelling of liquid metal divertor: from COMPASS tokamak towards Upgrade. Physica Scripta 96 124013 (2021)
[2] R. Dejarnac, et al.: Overview of power exhaust experiments in the COMPASS divertor with liquid metals. Nuclear Materials and Energy (2020) Vol. 25.
[3] J. Horacek, et al.: Modeling of COMPASS tokamak divertor liquid metal experiments. Nuclear Materials and Energy, 2020, Vol. 25
[4] A. Eksaeva, et al.: ERO2.0 modelling of the effects of surface roughness on molybdenum erosion and redeposition in the PSI-2 linear plasma device. Phys. Scr.2020 014057
[5] M. Poradzinski, et al.: Integrated core-SOL-divertor modelling for DEMO with tin divertor. Fusion Engineering and Design 124 (2017) 248-251