The superconducting tokamak JT-60SA is being built in Naka (Japan) under the Broader Approach Satellite Tokamak Programme jointly by Europe and Japan, and under the Japanese national programme. JT-60SA has an important supporting mission for the development of fusion energy: designed to achieve long pulses (100 s) and break-even equivalent plasmas, challenging high-beta operation beyond the no-wall limit. It will help in both the exploitation of ITER and in the definition of an optimized DEMO design. The device will be equipped with off-axis negative-NBI at 0.5 MeV beam energy, allowing current profile tailoring for advanced tokamak scenarios with fully noninductive current drive. The focus of the work is set on high ?N scenarios, in which kink-like instabilities (e.g., one or more RWMs) are potentially unstable and possibly lead to disruptions. In the framework of a joint European-Japanese collaboration, coordinated effort on MHD stability and control modelling is ongoing for the safe realization and exploitation of high-betaN plasmas. These scenarios offer a great opportunity to test and verify present models of RWM physics. The drift-kinetic damping model in particular will be considered in the present work, with a stability study in Scenario 5.1 -- like plasmas carried out with MARS-F/K. The challenge of active control is also addressed, taking advantage of the set of RWM control coils that JT-60SA will have. A dynamic simulator, based on the CarMa code, has been developed for feedback control modelling. A demonstration of this tool is given in one of the aforementioned plasmas, showing potential applications, results and latest developments.

Resistive Wall Mode Physics and Control Challenges in JT-60SA High Beta N Scenarios

Marchiori G;
2018

Abstract

The superconducting tokamak JT-60SA is being built in Naka (Japan) under the Broader Approach Satellite Tokamak Programme jointly by Europe and Japan, and under the Japanese national programme. JT-60SA has an important supporting mission for the development of fusion energy: designed to achieve long pulses (100 s) and break-even equivalent plasmas, challenging high-beta operation beyond the no-wall limit. It will help in both the exploitation of ITER and in the definition of an optimized DEMO design. The device will be equipped with off-axis negative-NBI at 0.5 MeV beam energy, allowing current profile tailoring for advanced tokamak scenarios with fully noninductive current drive. The focus of the work is set on high ?N scenarios, in which kink-like instabilities (e.g., one or more RWMs) are potentially unstable and possibly lead to disruptions. In the framework of a joint European-Japanese collaboration, coordinated effort on MHD stability and control modelling is ongoing for the safe realization and exploitation of high-betaN plasmas. These scenarios offer a great opportunity to test and verify present models of RWM physics. The drift-kinetic damping model in particular will be considered in the present work, with a stability study in Scenario 5.1 -- like plasmas carried out with MARS-F/K. The challenge of active control is also addressed, taking advantage of the set of RWM control coils that JT-60SA will have. A dynamic simulator, based on the CarMa code, has been developed for feedback control modelling. A demonstration of this tool is given in one of the aforementioned plasmas, showing potential applications, results and latest developments.
2018
Istituto gas ionizzati - IGI - Sede Padova
JT-60SA
Fusion Energy
High Beta N Scenarios
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/359818
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