Comparison between 3D eddy current patterns in Tokamak in-vessel components generated by disruptions
During plasma disruption events in Tokamaks, a large amount of magnetic energy is associated with the transfer of plasma current into eddy currents in the passive structures. In the International Thermonuclear Experimental Reactor (ITER) programme two design concepts have been proposed. One approach (ITER CDA design) is based on copper stabilization loops (ie twin loops) attached to box-shaped blanket segments, electrically and mechanically separated along the toroidal direction. For another design concept (ITER EDA design) based on lower plasma elongation there is no need for specific stabilization loops. The passive stabilization is obtained by toroidally continous components (ie the plasma facing wall of the blanket segments allows a continuity along the toroidal direction).
Bibliographic Reference: Paper presented: COMPUMAG, Berlin (DE), July 10-13, 1995
Availability: Available from (1) as Paper EN 39785 ORA
Record Number: 199610720 / Last updated on: 1996-08-06
Original language: en
Available languages: en