Executions of a Fusion Drift Kinetic Equation Solver on Grid

Calculating neoclassical (NC) transport is a fundamental part of the complete simulation cycle of the behavior of plasmas inside all tokamaks and stellerators. Also, due to NC transport is mainly determined by the magnetic properties of the device, its study is mandatory to ensure the efficiency of a certain coil configuration before it is implemented in a Fusion reactor. Thus, improvements to already constructed devices and certain design decisions for newer ones such as W7-X, NCSX or QPS will be made based on estimations of NC transport. In this work, we present the porting process to the Grid of the Drift Kinetic Equation solver code, widely accepted by the Fusion Community, devoted to obtain the monoenergetic diffusion coefficients of NC transport. The advantage of this code over the Monte Carlo applications already in production on Grid, is that it allows the estimation of all the transport coefficients, not only the diagonal ones. The tests and results obtained have been applied to the TJ-II Flexible Heliac at National Fusion Laboratory (Spain) by using the EELA-2 infrastructure.