Towards fully authentic modelling of ITER divertor plasmas
Ignited Next Step tokamaks such as NET or ITER are expected to use a poloidal magnetic divertor to facilitate exhaust of plasma particles and energy. This report describes a development coupling together with detailed computational models for both plasma and recycled neutral particle transport processes, to produce highly detailed and consistent design solutions. A particular aspect is involvement of an accurate specification of edge magnetic geometries, determined by an original equilibrium discretisation code, LINDA. Initial results for a prototypical 22MA ITER double-null configuration are presented. Uncertainties in such modelling are considered, especially with regard to intrinsic physical scale lengths. Similar results produced with a simpler, analytical treatment of recycling are also compared. Finally, a further extension allowing true oblique target sections is anticipated.
Bibliographic Reference: Article: 18th European Conference on Controlled Fusion and Plasma Physics, Vol. III (1991) pp. 197-200
Record Number: 199111421 / Last updated on: 1994-12-02
Original language: en
Available languages: en