作者: Antonio Juan Rubio-Montero , Francisco M. Castejon Magana , Manuel Aurelio Rodriguez-Pascual , Esther Montes Prado , Rafael Mayo Garcia
关键词: Magnetic confinement fusion 、 Electromagnetic coil 、 Computational science 、 Statistical physics 、 Grid 、 Physics 、 Stellarator 、 Solver 、 Harmonics 、 Monte Carlo method 、 Transport coefficient
摘要: Neoclassical (NC) transport calculations are necessary for the complete simulation cycle of behavior plasmas inside both tokamaks and stellarators, which more complex to be performed on latest. In addition, due fact that NC is mainly determined by magnetic properties device (mathematically designed number Fourier harmonics needed describe confining field), its study mandatory ensure efficiency a certain coil configuration before it implemented in fusion reactor. Thus, improvements already constructed devices design decisions new ones, such as W7-X, NCSX, or QPS, have been made based estimations transport, among other criteria. this sense, compromise between modes polynomials distribution function required computing time obtain reliable estimates must. This paper presents porting process Grid computational optimization Drift Kinetic Equation Solver code, devoted monoenergetic diffusion coefficients well first coupled prototype estimating with code release. The advantage over Monte Carlo applications production allows estimation all coefficients, not only diagonal ones. tests results obtained applied TJ-II Flexible Heliac, stellarator operation at National Fusion Laboratory (Spain), using EELA-2 Project infrastructure.