The US will contribute 100% towards the disruption mitigation system (up to a capped value).
The system has two functions: 1) limiting the impacts of plasma current disruptions to the tokamak vacuum vessel, first wall blankets and other in-vessel components, and 2) suppressing the formation and deleterious effects of high energy runaway electrons. The mitigation and suppression are expected to be accomplished by rapid shattered pellet injection (SPI).
For more information, contact:
Dave Rasmussen - Pellet Injection, Disruption Mitigation and Residual Gas Analyzer Team Leader - US ITER Project Office
email@example.com | 865-574-1158
- Vacuum Auxiliary and Roughing Pumps Systems
- Steady State Electrical Network
- Central Solenoid
- Toroidal Field Conductor
- Ion Cyclotron Heating Transmission Lines
- Instrumentation and Controls
- Pellet Inject (Fueling) System
- Tokamak Exhaust Processing System
- Electron Cyclotron Heating Transmission Lines
- Tokamak Cooling Water System