Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
271810 | Fusion Engineering and Design | 2011 | 4 Pages |
In ITER, wall damage after the disruptions can be mitigated using preventive massive gas injection (MGI) of noble gases into confined plasma. In the plasma the injected gas gets ionized and the core contamination results in fast loss of energy by radiation which distributes the wall load in a propitious way. For the modeling of MGI the tokamak code TOKES has been applied. This work reports further development of its models. The simulations earlier limited by the confinement region are expanded over the whole vessel of arbitrary wall shape. A simplified plasma model earlier employed for MGI is replaced by more adequate radiative model with dynamically changing level populations of plasma species. The processes in the plasma such as longitudinal motion, cross thermal conductivity and striking the wall are simulated neglecting wall response. The upgraded code is validated against an argon injection experiment of tokamak DIII-D.