Plasma physics and control studies planned in JT-60SA for ITER and DEMO operations and risk mitigation

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The most efficient and promising operational regime for the International Thermonuclear Experimental Reactor tokamak is the high-confinement mode. In this regime, however, periodic relaxations of the plasma edge can occur. These edge-localized modes pose a ...

We report the results of an exploratory design study for Nitronic 50 (N50) Toroidal Field (TF) coils for the EU-DEMO fusion power plant. N50 is a super-austenitic steel that has a yield stress (𝝈 𝒚) of up to 1500 MPa at 4 K, 50% higher than the conventiona ...

The poloidal field (PF) magnet system of the Divertor Tokamak Test (DTT) facility consists of 6 superconducting coils with full top-down symmetry, realized in Nb3Sn (PF1 and PF6) and NbTi (PF2, PF3, PF4 and PF5). To validate the NbTi PF coil design, short ...

In ITER, to mitigate the deleterious effects of plasma disruptions, massive quantities of radiating impurities will be injected into the disrupting plasma by shattered pellet injectors (SPI) to pre-emptively radiate away the stored thermal and magnetic ene ...

The Central Solenoid (CS) is at the core of the EU DEMO tokamak, and has a strong impact on the tokamak design and the overall machine size. By ramping its current, the CS generates a change of magnetic flux, which initiates the plasma, and induces and con ...

Global simulations of electromagnetic turbulence in circular-flux-surface tokamak and ASDEX-Upgrade geometry, tearing instabilities and their combination with the electromagnetic turbulence, nonlinear Alfvenic modes in the presence of fast particles and th ...

The JET 2019-2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully a ...

Using recently installed scrape-off layer diagnostics on the tokamak a configuration variable, we characterise the poloidal and parallel properties of turbulent filaments. We access both attached and detached divertor conditions across a wide range of core ...

Plasma physics and control studies planned in JT-60SA for ITER and DEMO operations and risk mitigation

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Effect of energetic ions on edge-localized modes in tokamak plasmas

Nitronic 50 Steel as a Structural Material for EU-DEMO's Toroidal Field Coils

Test results of the DTT poloidal field conductor samples in SULTAN: DC and AC characterization

Radiation asymmetry in JET disruption mitigation experiments with shattered pellet injection

Parametric Studies of the EU DEMO Central Solenoid

Gyrokinetic particle-in-cell simulations of electromagnetic turbulence in the presence of fast particles and global modes

Overview of JET results for optimising ITER operation

Cross-field and parallel dynamics of SOL filaments in TCV

Measurement of the instability threshold for Toroidal Alfven Eigenmodes as function of the ion grad B-drift direction in JET tokamak plasmas