Plasma regimes and research goals of JT-60SA towards ITER and DEMO

Abstract

The JT-60SA device has been designed as a highly shaped large superconducting tokamak with a variety of plasma actuators (heating, current drive, momentum input, stability control coils, resonant magnetic perturbation coils, W-shaped divertor, fuelling, pumping, etc) in order to satisfy the central research needs for ITER and DEMO. In the ITER- and DEMO-relevant plasma parameter regimes and with DEMO-equivalent plasma shapes, JT-60SA quantifies the operation limits, plasma responses and operational margins in terms of MHD stability, plasma transport and confinement, high-energy particle behaviour, pedestal structures, scrape-off layer and divertor characteristics. By integrating advanced studies in these research fields, the project proceeds ‘simultaneous and steady-state sustainment of the key performances required for DEMO’ with integrated control scenario development applicable to the highly self-regulating burning high-β high bootstrap current fraction plasmas.

ECH and ECCD effects on NTMs stabilization by ECRF in JT-60SA tokamak

“…Magnetic equilibria, temperature and density profiles [1] used as input of GRAY code are shown in figure 2. GRAY performs the computation of the Quasi Optical propagation, the power absorption and driven current of an astigmatic Gaussian beam of EC waves in a general tokamak equilibrium, taking into account trapped particle effects and the full wave polarization.…”

“…JT-60SA is the large fully superconducting tokamak being built under the Broader Approach Satellite Tokamak Programme jointly by Europe and Japan, and under the Japanese national program to support the ITER programme and DEMO design phase [1]. In the framework of the EU and JA combined work on the Research Plan revision [2] of JT-60SA the capability to well localize heating and current drive has been considered for various physics studies, such as the neoclassical tearing modes (NTMs) instabilities control, key issue to sustain high beta plasmas in fusion devices.…”

Development of a dual frequency (110/138 GHz) gyrotron for JT-60SA and its extension to an oscillation at 82 GHz

“…The millimetre wave frequency of 110 GHz will be used in JT-60SA for reusing the existing components as much as possible, and this frequency is useful for ECH/ECCD at the toroidal magnetic field of ~ 1.7 T, e.g. a high-beta scenario of JT-60SA (scenario 5) [13]. Recently, an application of a dual-frequency ECH/ECCD system in JT-60SA has been discussed [14] since the frequency of 130 -140 GHz is useful for ECH/ECCD at the toroidal magnetic field of 2.3 T, which is the maximum toroidal magnetic field in JT-60SA.…”

Study of Plasma Equilibrium Control for JT-60SA using MECS

“…A magnetohydrodynamic (MHD) equilibrium control simulator (MECS) has been developed to study techniques for plasma equilibrium control in JT-60SA [1][2][3]. A plasma shape reconstruction system had not been incorporated in the previous MECS, and the power supply capability had not been taken into account in the tokamak simulator.…”