Model based optimization of Advanced Tokamak plasma start-up
ORAL
Abstract
AT scenarios offer improved stability, confinement and pulse length compared to standard scenarios due to an increase of the plasma’s bootstrap current jbs∝q∇p. They are accessed by externally manipulating the safety factor profile q, which can be applied during the current ramp-up, or after an equilibrium is reached. The former allows for a longer discharge and more unconventional current distributions, but due to the volatility of the early plasma, creating such a scenario experimentally, with feed-forward control usually takes a lot of trial and error.
To combat this, a model has been developed in the transport code ASTRA, capable of accurately predicting the plasma response to actuator changes with a run-time of only a few minutes. This allows to quickly test large amounts of possible actuator configurations. The model includes Gyro-Bohm based core transport, edge transport according to a recently developed scaling law as well as the L/H-transition based on the heating power at the separatrix. Good agreement between simulation and experiment has been achieved.
The suitability of this model to design such a scenario has successfully been tested at ASDEX-U. Further improvement of the physics models and assumptions towards predictive capability for future machines is planned.
To combat this, a model has been developed in the transport code ASTRA, capable of accurately predicting the plasma response to actuator changes with a run-time of only a few minutes. This allows to quickly test large amounts of possible actuator configurations. The model includes Gyro-Bohm based core transport, edge transport according to a recently developed scaling law as well as the L/H-transition based on the heating power at the separatrix. Good agreement between simulation and experiment has been achieved.
The suitability of this model to design such a scenario has successfully been tested at ASDEX-U. Further improvement of the physics models and assumptions towards predictive capability for future machines is planned.
*This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 and 2019–2020 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.
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Presenters
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Raphael Schramm
- Max-Planck-Institute for Plasma Physics