In this paper, DEMO-like shaped plasma equilibria are defined for RFX-mod2 tokamak operations by using the Inverse Equilibrium Tool (IET code). IET allows for the computation of the coil currents needed to obtain a predetermined plasma shape with well defined plasma global parameters (i.e. total plasma current and total poloidal magnetic flux at the boundary) by solving a constrained minimization problem. The new shape conditions would allow achieving higher plasma current and plasma density values at the same toroidal magnetic field and safety factor limits of previous RFX-mod tokamak operations. The feasibility of these new equilibria is explored in terms of coil current requirements and vertical stability analysis. This study shows that RFX-mod2 is a flexible device, able to perform DEMO-like shaped tokamak operations with low requirements on both magnitude and distribution of active coil currents.
Modelling of RFX-mod2 tokamak equilibria with DEMO-like shape conditions and negative triangularity
Abate D.; Marchiori G.; Bettini P.; Villone F.
ID | 428484 |
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DOI | 10.1088/1361-6587/ab93a5 |
PRODUCT TYPE | Journal Article |
LAST UPDATE | 2022-02-08T11:47:49Z |