Modelling nonlocal kinetic transport in 2D fluid SOL simulations
Modelling nonlocal kinetic transport in 2D fluid SOL simulations
Simulation
Magnetic Confinement

Modelling nonlocal kinetic transport in 2D fluid SOL simulations

The anticipated high temperature, low-collisonality SOL plasmas of tokamak fusion reactors require capturing nonlocal kinetic energy transport effects in order to have confidence in the predictions from 2D transport codes. This project seeks to apply a reduced-kinetic parallel transport model in an existing large-scale 2D SOL code, to study reactor-relevant plasma conditions. The SNB model, implemented in the BOUT++ framework, will be applied to calculate the parallel thermal transport in the Hermes-3 code. The MAST-U device is considered, then extrapolated up to reactor conditions, and used to study the impact on predictions of upstream plasma profiles and neutral penetration/fuelling.

Principal Investigator
Jerry Hughes; A white man with graying hair smiles at the camera. He wears a light blue button up in front of a row of computers.
Jerry Hughes
Principal Research Scientist and Deputy Division Head, Magnetic Fusion Experiments
Team
A young white man with dark hair pulled back wears a navy button down and smiles sligtly
Michael Wigram
Michael Wigram
01
Importance of research

The anticipated high temperature, low-collisonality SOL plasmas of tokamak fusion reactors require capturing nonlocal kinetic energy transport effects in order to have confidence in the predictions from 2D transport codes. This project seeks to apply a reduced-kinetic parallel transport model in an existing large-scale 2D SOL code, to study reactor-relevant plasma conditions. The SNB model, implemented in the BOUT++ framework, will be applied to calculate the parallel thermal transport in the Hermes-3 code. The MAST-U device is considered, then extrapolated up to reactor conditions, and used to study the impact on predictions of upstream plasma profiles and neutral penetration/fuelling.

Accurate predictions of tokamak edge plasmas, as well as neutral dynamics and fuelling efficiency, relies on an accurate prediction of the plasma energy transport. Fluid plasma codes, that miss key kinetic effects in energy transport, may lead to significant error when used for predictions of future reactor devices. In low-collisionality conditions, supra-thermal electrons with very long mean-free-paths carry most of the parallel plasma energy, and energy transport becomes “nonlocal”. High energy gain fusion devices will exhibit for the first time both high opaqueness to neutrals and a very low collisionality SOL. It is presently envisioned that in either conventional or spherical tokamak pilot plants, main chamber SOL plasma temperatures will be high enough to invalidate the fluid approach, with kinetic effects becoming increasingly important to parallel heat transport. Full kinetic simulations are computationally expensive. ‘Reduced-kinetic’ models offer an alternative method for calculating the parallel heat flux component within fluid codes, with greater accuracy towards the “true” kinetic result at reduced computational cost. Employing such models in 2D edge plasma codes offers the potential to improve the accuracy of our predictions for future fusion reactors, and therefore increase their chances of success.