ITER Shape Controller and Transport Simulations
We currently use the CORSICA integrated modeling code for scenario studies for both the DIII-D and ITER experiments. In these simulations, free- or fixed-boundary equilibria are simultaneously converged with thermal evolution determined from transport models providing temperature and current density profiles. Using a combination of fixed boundary evolution followed by free-boundary calculation to determine the separatrix and coil currents. In the free-boundary calculation, we use the state-space controller representation with transport simulations to provide feedback modeling of shape, vertical stability and profile control. In addition to a tightly coupled calculation with simulator and controller imbedded inside CORSICA, we also use a remote procedure call interface to couple the CORSICA non-linear plasma simulations to the controller environments developed within the Mathworks Matlab/Simulink environment. We present transport simulations using full shape and vertical stability control with evolution of the temperature profiles to provide simulations of the ITER controller and plasma response.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 942034
- Report Number(s):
- UCRL-JRNL-231396; FEDEEE; TRN: US0807517
- Journal Information:
- Fusion Engineering and Design, Vol. 83, Issue 2-3; ISSN 0920-3796
- Country of Publication:
- United States
- Language:
- English
Similar Records
Prediction of divertor heat flux width for ITER pre-fusion power operation using BOUT++ transport code
CORSICA modelling of ITER hybrid operation scenarios