The RFX - mod device has been recently operated as a Tokamak with circular and shaped plasmas [1] . After preliminary assessment of plasma shape and position controller, the operations were focused to increase the plasma performances towards the H - mode regime. Thus experimental campaign s spanning different plasma regimes, from the naturally low - beta2 to th e edge biasing induced H - mode plasma [2] , were performed in the last year. The availability of linearized plasma response models of each new configuration achieved may be valuable for prediction and possible improvement of controller performances. The analysis le d to the development of a general iterative procedure for the production of accurate plasma linearized models for different experimental conditions by using the CREATE - L code [3] . The RFX - mod shape controller can therefore be assessed and tuned by means of these linearized models covering a wide class of plasma configurations. Furthermore the models can be used to improve the calibration of the magnetic diagnostics involved in the experiment. From this starting point a further more detailed model ling activity with increasing level of complexity can be addressed by taking into account the 3D volumetric wall effects by means of CarMa0 code [4] and non - linear time evolution of the entire plasma discharge with 3D wall by using the evolutionary non - lin ear code CarMa0NL [5] .
Modelling of RFX-mod shaped tokamak plasmas: from low-beta2 plasmas towards H-mode regime
Marchiori G;
2017
Abstract
The RFX - mod device has been recently operated as a Tokamak with circular and shaped plasmas [1] . After preliminary assessment of plasma shape and position controller, the operations were focused to increase the plasma performances towards the H - mode regime. Thus experimental campaign s spanning different plasma regimes, from the naturally low - beta2 to th e edge biasing induced H - mode plasma [2] , were performed in the last year. The availability of linearized plasma response models of each new configuration achieved may be valuable for prediction and possible improvement of controller performances. The analysis le d to the development of a general iterative procedure for the production of accurate plasma linearized models for different experimental conditions by using the CREATE - L code [3] . The RFX - mod shape controller can therefore be assessed and tuned by means of these linearized models covering a wide class of plasma configurations. Furthermore the models can be used to improve the calibration of the magnetic diagnostics involved in the experiment. From this starting point a further more detailed model ling activity with increasing level of complexity can be addressed by taking into account the 3D volumetric wall effects by means of CarMa0 code [4] and non - linear time evolution of the entire plasma discharge with 3D wall by using the evolutionary non - lin ear code CarMa0NL [5] .I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
