Large tangential electric fields in plasmas close to temperature screening
Plasma Physics and Controlled Fusion IOP Publishing 60:7 (2018) 074004
Abstract:
Low collisionality stellarator plasmas usually display a large negative radial electric field that has been expected to cause accumulation of impurities due to their high charge number. In this paper, two combined effects that can potentially modify this scenario are discussed. First, it is shown that, in low collisionality plasmas, the kinetic contribution of the electrons to the radial electric field can make it negative but small, bringing the plasma close to impurity temperature screening (i.e., to a situation in which the ion temperature gradient is the main drive of impurity transport and causes outward flux); in plasmas of very low collisionality, such as those of the large helical device displaying impurity hole (Ida et al (The LHD Experimental Group) 2009 Phys. Plasmas 16 056111; Yoshinuma et al (The LHD Experimental Group) 2009 Nucl. Fusion 49 062002), screening may actually occur. Second, the component of the electric field that is tangent to the flux surface (in other words, the variation of the electrostatic potential on the flux surface), although smaller than the radial component, has recently been suggested to be an additional relevant drive for radial impurity transport. Here, it is explained that, especially when the radial electric field is small, the tangential magnetic drift has to be kept in order to correctly compute the tangential electric field, that can be larger than previously expected. This can have a strong impact on impurity transport, as we illustrate by means of simulations using the newly developed code kinetic orbit-averaging-solver for stellarators, although it is not enough to explain by itself the behavior of the fluxes in situations like the impurity hole.Effects of misaligning the probe beam and magnetic field in Doppler backscattering measurements
45th EPS Conference on Plasma Physics, EPS 2018 2018-July (2018) 1436-1439
Optimized up-down asymmetry to drive fast intrinsic rotation in tokamaks
Nuclear Fusion Institute of Physics 58:2 (2017) 026003
Abstract:
Breaking the up-down symmetry of the tokamak poloidal cross-section can significantly increase the spontaneous rotation due to turbulent momentum transport. In this work, we optimize the shape of flux surfaces with both tilted elongation and tilted triangularity in order to maximize this drive of intrinsic rotation. Nonlinear gyrokinetic simulations demonstrate that adding optimally-tilted triangularity can double the momentum transport of a tilted elliptical shape. This work indicates that tilting the elongation and triangularity in an ITER-like device can reduce the energy transport and drive intrinsic rotation with an Alfv\'{e}n Mach number on the order of $1\%$. This rotation is four times larger than the rotation expected in ITER and is sufficient to stabilize MHD instabilities. It is shown that this optimal shape can be created using the shaping coils of several experiments.Overview of progress in European medium sized tokamaks towards an integrated plasma-edge/wall solution a aIn the future we will refer to the author list of the paper as the EUROfusion MST1 Team.
Nuclear Fusion IOP Publishing 57:10 (2017) 102014
Ion-scale turbulence in MAST: anomalous transport, subcritical transitions, and comparison to BES measurements
Plasma Physics and Controlled Fusion Institute of Physics 59:11 (2017) 114003