A new test method of AC loss assessment for fusion conductors

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Internal transport barriers (ITB) form through turbulence suppression, often observed when the safety factor profile exhibits an off-axis minimum. This work aims at improving our understanding of the conditions enabling the development of an ITB, using a m ...

The ability to drive the plasma potential in a magnetized plasma column using strongly negatively biased emissive cathode is experimentally demonstrated. By analysing an extensive experimental dataset, and in particular the evolution of the radial profiles ...

Combined high-fusion performance and long-pulse operation is one of the key integration challenges for fusion energy development in magnetic devices. Addressing these challenges requires an integrated vision of physics and engineering aspects with the purp ...

The design point that had been chosen for EU DEMO in 2016 is reviewed here and a modification is proposed with a lower aspect ratio. Previously the same aspect ratio, A, was chosen for EU DEMO as in major tokamak experiments including ITER (A = 3.1), and, ...

The shift towards DC power distribution networks, enabled by power electronics technologies, is changing the nature of electrical power systems. Nowadays, DC power distribution networks can effectively support the high penetration of distributed energy res ...

In order to cope with the decarbonization challenge faced by many countries, fusion is one of the few alternatives to fossil fuels for the production of electricity. Two devices invented in the middle of the previous century have emerged as the most promis ...

Nuclear fusion presents a promising clean energy source to mitigate future energy crises, with magnetic confinement fusion well-positioned to provide a baseload scenario to power future reactors. The unmitigated power exhaust of such reactors threatens its ...

The need of full transposition of the current carrying elements (strands) in large cables is frequently retained as top design criterion for conductors operating in pulsed mode. However, when the transposition error, i.e., the inductance difference among t ...

The European Roadmap to Fusion Electricity (Federici et al., 2018) [1] details the path to complete within the next three decades the DEMOnstration power plant, DEMO, aiming to a net gain of Energy Q=40. The 2018 DEMO baseline considers a 2 GW tokamak devi ...

The Tokamak a` Configuration Variable (TCV) coil converters are fed, during the plasma pulse, by a flywheel generator (FG) providing the AC voltages few seconds before the plasma pulse. The synchronization with the 120 Hz frequency delivered by the FG, var ...

Tokamak devices aim to magnetically confine a hydrogen plasma at sufficiently high pressure to achieve net energy production from nuclear fusion of light isotopes. Predictive modeling and optimization is crucial for reliable operation of tokamak reactors, ...

Nowadays, direct current (DC) technology is increasing its presence in alternating current (AC) power systems. This trend is enabled by the progress in energy conversion through semiconductor devices and power electronics. Therefore, it is possible to imag ...

Inductive magnetic sensors are needed for tokamak operation to provide the low-frequency (LF) measurements leading to the equilibrium reconstruction and to monitor the higher frequency (HF) instabilities; the HF magnetic sensors are often also used as a ba ...

Fusion occurs when light nuclei combine to form heavier nuclei. The energy released in this process powers the stars and can provide humankind with a safe, sustainable, and clean source of baseload electricity, a valuable tool in the fight against climate ...

Many future fusion devices will rely heavily, if not solely, on electron cyclotron (EC) heating subsystems to provide bulk heating, instability control (neoclassical tearing mode (NTM) stabilization), and thermal instability control. Efficient use of the i ...

Soft switching in dual-active-bridge (DAB) converters enables their efficient operation at high frequencies, where the reduction in the size of magnetic components could result in ultra-high power densities. Nonetheless, losing soft-switching at high frequ ...

Paschen failures in ITER, W7-X and JT60 superconducting coils at the acceptance tests have shown that it is highly desirable to lower the coil discharge voltage (U-d) of the DEMO Toroidal Field (TF) coils. Another benefit of lowering the U-d might be the r ...

The ADITYA-U tokamak (R-0 = 0.75 m, a = 0.25 m) is designed to shape plasma column in both single and double null diverter configurations. It is quite well known that sustaining a shaped plasma in tokamak requires very good plasma column position control, ...

The aim of this thesis is to investigate the mechanical and thermal behaviour of HTS coated conductor cables for EUROfusion DEMO magnets. One of the issue in large HTS magnets is the safety against a quench. A quench is a sudden thermal runway in which the ...

The stepped-pressure equilibrium code (SPEC) (Hudson et al., Phys. Plasmas, vol. 19, issue 11, 2012, 112502) is extended to allow the computation of multi-region, relaxed magnetohydrodynamics (MRxMHD) equilibria at prescribed toroidal current profile. Toro ...

A new test method of AC loss assessment for fusion conductors

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Global electromagnetic gyrokinetic simulations of internal transport barriers in reversed-shear tokamaks

Plasma Potential Control in a Magnetized Plasma Column Using a Thermionic Cathode

Long plasma duration operation analyses with an international multi-machine (tokamaks and stellarators) database

Re-design of EU DEMO with a low aspect ratio

DC Power Distribution Networks with Direct Current Transformers

Global fluid simulations of plasma turbulence in stellarators

Experimental study and interpretative modelling of the Power Exhaust in Configurations with Multiple X-Points in TCV

Performance Comparison of Cables With Partial Transposition

The MAgnet Design Explorer algorithm (MADE) for LTS, Hybrid or HTS toroidal and poloidal systems of a tokamak with a view to DEMO

Control upgrade for the TCV coils power supplies

Full-discharge simulation and optimization with the RAPTOR code, from present tokamaks to ITER and DEMO

Modeling, Optimization and Design of High Power Medium Frequency Transformers

First developments towards producing inductive magnetic sensors using state-of-the-art photolithography techniques

Essay: Overcoming the Obstacles to a Magnetic Fusion Power Plant

High power mm-wave loss measurements of ITER ex-vessel waveguide components at the FALCON test facility at the Swiss Plasma Center

Enhanced-DAB Converter: Comprehensive Design Evaluation

Preliminary Design of a High Current R&W TF Coil Conductor for the EU DEMO

Real-time feedback control system for ADITYA-U horizontal plasma position stabilisation

Electromechanical investigations and quench experiments on sub-size HTS cables for high field EU-DEMO Central Solenoid

Computation of multi-region, relaxed magnetohydrodynamic equilibria with prescribed toroidal current profile