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Grid Fusion Code for Drift Kinetic Equation Solver in Fusion Reactors

This work presents the gridification of a Drift Kinetic Equation solver (DKEs) used in simulating neoclassical transport for stellarators and tokamaks. Unlike Monte Carlo methods that require extensive memory, DKEs offer a closer approach to analytic solutions. We detail the performance and portability improvements achieved through the gridification process on the CIEMAT internal grid, including results from tests conducted on the TJ-II Flexible Heliac at the National Fusion Laboratory in Spain. Neoclassical transport coefficients are indexed in a public database per fusion device.

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Grid Fusion Code for Drift Kinetic Equation Solver in Fusion Reactors

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  1. A Grid fusion code for the Drift Kinetic Equation solver A.J. Rubio-Montero, E. Montes, M.Rodríguez, F.Castejón, R.Mayo CIEMAT. Avda Complutense, 22. Madrid (SPAIN) Diffusion coefficients calculated by DKES by collisionallity for a single electric field SGI 3800 (50 MPI processors 600Mhz) CIEMAT Internal Grid (limited to 25 slots among 5 heterogeneous resources) EELA + Internal + others (limited to 60 slots among 12 available resources) Performance (jobs x second) Jobs completed Abstract Several Drift Kinetic Equation solvers (DKEs) codes are used to simulate the neoclassical transport for the stellerators and tokamaks fusion reactors. These applications offer an approach more near to analytic solution than Monte Carlo methods, but usually requiring a great amount of memory, making their porting to Grid difficult. This work explains the gridification process of a DKEs code widely accepted by the Fusion community. Also, performance and portability gains are evaluated. The tests and results obtained have been applied to the TJ-II Flexible Heliac at National Fusion Laboratory (Spain) by using mainly the EELA-2 infrastructure. Neoclassical transport coefficients for all possible magnetic surface, temperature, density are indexed in a public database by fusion device. 36.8% 105.2%

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