"Free-boundary simulations of ITER advanced scenarios"
Event details
| Date | 16.05.2013 |
| Hour | 14:30 › 15:30 |
| Speaker | Karim Besseghir, CRPP-EPFL |
| Location |
CRPP, PPB 019
|
| Category | Conferences - Seminars |
The successful operation of ITER advanced scenarios is likely to be a major step forward towards controlled fusion. ITER advanced scenarios raise specific challenges that are not encountered in presently-operated tokamak. Three such challenges are presented.
Firstly, a novel approach to current density profile modification is introduced and the results of exploratory studies are exposed. Secondly, it is argued that the design of ITER scenario should be automated. Such scenario design automation is tackled using optimal control techniques and the results are discussed. Real-time optimisation schemes are discussed and it is concluded that the necessary conditions of optimality tracking approach may potentially be appropriate for ITER operation, thus offering a viable closed-loop optimal control approach. Finally, the DINA-CH&CRONOS full tokamak simulator is used to simulate the operation of the ITER hybrid and steady-state scenarios. It is concluded that the present ITER design is appropriate for performing a hybrid scenario pulse lasting more than 1000s, with a flat-top plasma current of 12MA, and a fusion gain of Q=8. Similarly, a steady-state scenario without internal transport barrier, with a flat-top plasma current of 10MA, and with a fusion gain of Q=5 can be realised using the present ITER design.
Firstly, a novel approach to current density profile modification is introduced and the results of exploratory studies are exposed. Secondly, it is argued that the design of ITER scenario should be automated. Such scenario design automation is tackled using optimal control techniques and the results are discussed. Real-time optimisation schemes are discussed and it is concluded that the necessary conditions of optimality tracking approach may potentially be appropriate for ITER operation, thus offering a viable closed-loop optimal control approach. Finally, the DINA-CH&CRONOS full tokamak simulator is used to simulate the operation of the ITER hybrid and steady-state scenarios. It is concluded that the present ITER design is appropriate for performing a hybrid scenario pulse lasting more than 1000s, with a flat-top plasma current of 12MA, and a fusion gain of Q=8. Similarly, a steady-state scenario without internal transport barrier, with a flat-top plasma current of 10MA, and with a fusion gain of Q=5 can be realised using the present ITER design.
Practical information
- Informed public
- Free
Organizer
- Prof. P. Ricci, CRPP
Contact
- Prof. P. Ricci, CRPP