Publications by James Paley | EPFL Graph Search

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A new paradigm is presented to reconstruct the plasma current density profile in a tokamak in real-time. The traditional method of basing the reconstruction on real-time diagnostics combined with a real-time Grad-Shafranov solver suffers from the difficult ...

Real time control of the plasma elongation and plasma current using electron cyclotron resonance heating (ECRH) actuators has been demonstrated on TCV. Tokamak plasmas may be elongated by off-axis ECRH. The associated flattening of the current density prof ...

Important advances have been made recently in the invention and application of experimental methods to control the sawtooth instability in tokamak plasmas. The primary means of control involves the application of either ion cyclotron resonance heating (ICR ...

Tokamak plasmas operating at high performance are limited by several MHD instabilities. The sawtooth instability limits the core plasma pressure and can drive the neoclassical tearing mode unstable, but also prevents accumulation of impurities in the core. ...

Modulation of the amplitude of externally injected electron cyclotron (EC) power is a frequent method used to determine the radial power deposition profile in fusion plasmas. There are many tools to analyze the plasma response to the power modulations unde ...

Developments in the real time control hardware on Tokamak à Configuration Variable (TCV) coupled with the flexibility of plasma shaping and electron cyclotron (EC) heating and current drive actuators are opening many opportunities to perform real time expe ...

Early tokamaks with circular cross-section plasmas were vertically stable in nature and no problems were reported on the control of the vertical position. However, the concept of vertically elongated plasma cross-section, with benefits to the energy confin ...

New experimental results on transient loads during ELMs and disruptions in present divertor tokamaks are described and used to carry out a extrapolation to ITER reference conditions and to draw consequences for its operation. In particular, the achievement ...

The magnetic energy balance and magnetic energy flows for plasma disruptions in which runaway plateau plasmas are formed and terminated at JET has been analysed and compared with that of runaway-free disruptions. The analysis shows that the energy loss pro ...

Real time control of heating systems is essential to maximize plasma performance and avoid or neutralize instabilities under changing plasma conditions. Several feedback control algorithms have been developed on the Tokamak a Configuration Variable (TCV) t ...

Divertor surface temperatures are significantly affected by the presence of deposited surface layers. This phenomenon can be used to monitor deposited layer evolution on a shot-by-shot basis. It was found that during an experimental campaign where the B x ...

James Paley

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Real-time physics-model-based simulation of the current density profile in tokamak plasmas

Real time control of the plasma current and elongation in tokamaks using ECRH actuators

Recent Advances in Sawtooth Control

Real time control of the sawtooth period using EC launchers

Multiple EC power deposition locations tracking by break-in-slope analysis in TCV plasmas

Real time control of plasmas and ECRH systems on TCV

Using APCS for Plasma Vertical Control at TCV

Transient heat loads in current fusion experiments, extrapolation to ITER and consequences for its operation

Magnetic energy flows during the current quench and termination of disruptions with runaway current plateau formation in JET and implications for ITER

From sawtooth to profile control: developing feedback control using ECRH/ECCD systems on the TCV tokamak

Transient heat loads in current fusion experiments, extrapolation to next step devices and consequences for their operation

Real time plasma current and elongation control using ECRH actuators

Outer divertor target deposited layers during reversed magnetic field operation in JET

Experiments with real-time controlled ECW on the TCV Tokamak

ELMs and disruptions in ITER: Expected Energy Fluxes on Plasma Facing Components from Multi-machine Experimental Extrapolations and Consequences for ITER Operation