ASTRA: Difference between revisions

Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with magnetic islands,” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.