Global models are useful in the analysis of fusion reactors due to the facility in computing and presenting the results in terms of comprehensive parameters. A general figure of merit, which encompasses all the relevant tokamak parameters, is introduced in this article by a convenient normalization of the global power balance equation. In this way, different hypothetical tokamak reactors can be...

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Gyrokinetic particle-in-cell simulation on a transport and microinstability time scale is performed with the ELMFIRE code for a small tokamak FT-2 with kinetic electrons. Turbulent modes are characterized based on their poloidal phase velocity, and tentative comparison with the Doppler reflectometric measurement is done for the poloidal mode rotation. Cyclone base case comparison with adiabatic...

Non-inductive current start-up experiments by using electron cyclotron heating and current drive (ECH/ECCD) technique has been conducted in the Compact Plasma-wall-interaction experimental Device (CPD), which is a small spherical tokamak device. By applying 8.2 GHz RF under steady external fields, plasma currents are generated and closed flux surface configurations are formed spontaneously. Two...

Abstract Within the effort on conceptual design of Divertor Test Tokamak (DTT) Neutral Beam Injector (NBI), Stray Field Shielding System (SFSS) for DTT NBI is under development, to suppress potentially harmful effects stray poloidal field from tokamak accelerated charged beam. Various possible solutions solve this problem are presented and compared, with a particular focus minimization procedur...

We set up a mapping procedure able to translate the evolution of radial profile fast ions, interacting with Toroidal Alfv\'en Eigenmodes, into dynamics an equivalent one dimensional bump-on-tail system. apply this technique reproduce ITER relevant simulations, which clearly outlined deviations from diffusive quasi-linear (QL) model. Our analysis demonstrates capability one-dimensional beam-plas...

Understanding the properties of high gain (alpha-dominated) fusion plasmas in an advanced toroidal configuration is the largest remaining open issue that must be addressed to provide the scientific foundation for an attractive magnetic fusion reactor. The critical parts of this science can be obtained in a compact high field tokamak which is also likely to provide the fastest and least expensiv...

Abstract Tokamak and inertial confinement fusion(ICF) are two kinds of devices to achieve fusion. Magnetic gravitational fields the drivers used in tokamak ICF, respectively. In other fusion like MIF, both them used. this work, different from these mentioned above, a new promising method confine plasma is proposed. Spacial distribution energy high-speed changing magnetic field simulated. This e...

Abstract Tokamaks are the most promising way for nuclear fusion reactors. Disruption in tokamaks is a violent event that terminates confined plasma and causes unacceptable damage to device. Machine learning models have been widely used predict incoming disruptions. However, future reactors, with much higher stored energy, cannot provide enough unmitigated disruption data at high performance tra...