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UKAEA-STEP-PR(25)252024
This paper discusses the importance of parallel and perpendicular magnetic field perturbations in gyrokinetic simulations of electromagnetic instabilities and turbulence at mid-radius in the burning plasma phase of the conceptual high-β, reactor-scale, tight-aspect- ratio tokamak STEP. Previous studies have revealed the presence of unstable hybrid…
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UKAEA-CCFE-PR(24)2662024
A new type of resonant magnetic perturbation (RMP), generated by helical coils, is proposed for controlling the edge localized mode (ELM) in H-mode tokamak plasmas. The helical coil optimization utilizes the MARS-F code (Liu et al 2000 Phys. Plasmas 7 3681) computed linear resistive fluid response of the plasma to the applied RMP field. The opti…
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UKAEA-CCFE-PR(24)2562024
An absolutely calibrated, visible imaging diagnostic has been deployed on the MAST spherical tokamak. Two sets of three colour channels are defined using a combination of stacked multi-cavity interference filters, colour-glass filter and a colour-pixel sensor. The system is compact with a single viewing pupil which facilitates unambiguous compariso…
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UKAEA-CCFE-PR(24)2142024
In order to test the capability of the full electromagnetic DYON to predict the plasma initiation feasibility of individual discharges and thus the operating space in the device, a dedicated experimental database was built in MAST-U by scanning the prefilled gas pressure $p_0$ and the induced loop voltage $V_{loop}$ (3 failed breakdown discharge…
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UKAEA-CCFE-PR(24)2132024
In this work, the first experimental attempts at controlling Edge Localised Modes (ELMs) via the application of resonant magnetic perturbations (RMPs) on theMAST Upgrade tokamak are reported. Moderate ELM mitigation was achieved in low betaN by the application of n=1 3D fields, at the cost of inducing a ’benign’ locked mode. At higher betaN how…
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UKAEA-STEP-CP(24)052023
The STEP (Spherical Tokamak for Energy Production) Programme aims to deliver a UK prototype fusion energy plant, targeting 2040, and a path to commercial viability of fusion. To deliver on this aim, we have performed initial scoping to identify the design point for a spherical tokamak prototype powerplant producing at least 100 MWe of…
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UKAEA-CCFE-PR(24)2482023
This work describes the usage of Error Field Correction coil system [Barlow I. et al 2001 Fusion Eng. Des. 58-59 189], which is a set of 4 coils located external to the vessel of the JET device, with the aim of introducing non-axisymmetric n=1 magnetic field perturbations in various targeted plasma experiments. Besides being used to characterize…
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UKAEA-CCFE-PR(24)2472023
The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challeng…
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UKAEA-CCFE-PR(24)2252023
JET’s frequency-modulated continuous wave (FMCW) reflectometers have been operating well with the current design since 2005 and density profiles are being automatically calculated intershot since then. However, the calculated profiles had long suffered from several shortcomings – poor agreement with other diagnostics; sometimes inappropriate…
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UKAEA-CCFE-PR(23)1872023
Solution reconstruction from limited number of measurements is useful in many areas of heat transfer applications. Unlike the standard problems, such reconstruction problems are ill-posed; thus, the non-uniqueness of solution and inherent instability severely complicates the modelling process. Consequently, more conventional inverse analysis method…
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