Community Research and Development Information Service - CORDIS


A new 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 three-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 column. These "contact currents", not considered in an ordinary eddy current analysis, are responsible for very high vertical forces on the reactor FW, which makes them one of the most dramatic occurrences in a tokamak discharge. The model is presented and discussed in this publication.

Additional information

Authors: CRUTZEN Y, JRC Ispra (IT);FANTECHI S, JRC Ispra (IT)
Bibliographic Reference: Paper presented: Third International Workshop on Electric and Magnetic Fields, Liege (BE), May 6-9, 1996
Availability: Available from (1) as Paper EN 39741 ORA
Record Number: 199610667 / Last updated on: 1996-06-21
Original language: en
Available languages: en