Impact of the passive stabilization system on the dynamic loads of the ITER first wall/blanket during a plasma disruption event
In next generation tokamak devices (ITER) passive stabilisation of the plasma is required to mitigate the consequences of the plasma vertical displacements and to reduce the occurrence of plasma disruptions. To this end two main design approaches have been considered. The first of these (adopted in the ITER CDA design) consists of copper stabilisation loops (i.e. twin loops) attached to box-shaped blanket segments which are electrically and mechanically separated along the toroidal direction. In the second design approach (for the ITER EDA design), relying on a lower plasma elongation, no specific stabilisation loops are required and the passive stabilisation is achieved by toroidally continuous components. In both cases electrodynamic loads arise in the blanket structures during plasma disruptions and/or vertical displacement events. A comparison between the two design approaches has been carried out from the eddy current and related load distribution viewpoint.
Bibliographic Reference: Paper presented: 3rd International Symposium on Fusion Nuclear Technology, Los Angeles (US), June 27 - July 1, 1994
Availability: Available from (1) as Paper EN 38230 ORA
Record Number: 199410495 / Last updated on: 1994-11-28
Original language: en
Available languages: en