Simulating the ITER Plasma Startup Scenario in the DIII-D Tokamak
DIII-D experiments have investigated ITER startup scenarios, including an initial phase where the plasma was limited on low field side (LFS) poloidal bumper limiters. Both the original ITER 'small-bore' (constant q{sub 95}) startup and a 'large-bore' lower internal inductance (l{sub i}) startup have been simulated. In addition, l{sub i} feedback control has been tested with the goal of producing discharges at the ITER design value, l{sub i}(3) = 0.85. These discharges have been simulated using the Corsica free boundary equilibrium code. High performance hybrid scenario discharges ({beta}{sub N} = 2.8, H{sub 98,y2} = 1.4) and ITER H-mode baseline discharges ({beta}{sub N} > 1.6, H{sub 98,y2} = 1-1.2) have been obtained experimentally in an ITER similar shape after the ITER-relevant startup.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 945672
- Report Number(s):
- LLNL-CONF-407829; TRN: US0901055
- Resource Relation:
- Journal Volume: 49; Journal Issue: 11; Conference: Presented at: 22nd IAEA-FEC, Geneva, Switzerland, Oct 13 - Oct 18, 2008
- Country of Publication:
- United States
- Language:
- English
Similar Records
Demonstration of ITER Operational Scenarios on DIII-D
Demonstration of ITER operational scenarios on DIII-D