Modelling and analysis of plasma-first wall contact during vertical instabilities in next-step tokamaks with a 3D eddy current code
A computer procedure, based on a simplified model of the phenomenon of plasma-first wall (FW) contact, has been developed to take into account the conductive transfer of electric current from the plasma halo to the FW during a vertical displacement event (VDE) in a next-step tokamak-type fusion device. The model has been introduced in a 3-dimensional (3D) eddy current code for electromagnetic (EM) analysis to account for the extra poloidal currents flowing in the reactor wall during the transient vertical displacements of the plasma. These contact currents are responsible for very high vertical forces on the reactor FW, which makes them one of the most dramatic occurrences in tokamak discharge.
Bibliographic Reference: Paper presented: 19th Symposium on Fusion Technology, Lisbon (PT), September 16-20, 1996
Availability: Available from (1) as Paper EN 40075 ORA
Record Number: 199611282 / Last updated on: 1996-11-11
Original language: en
Available languages: en