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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-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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UKAEA-CCFE-PR(23)1272023
The high source stability and brightness of field emission gun equipped scanning electron microscopes (SEM) makes them ideal for high-resolution digital image correlation (HRDIC). However, their high initial capital cost can be prohibitive for research organisations and groups. Conventional thermionic SEMs using either a tungsten hairpin or LaB
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UKAEA-CCFE-PR(23)152023
Pellet injection is used for fuelling and controlling discharges in tokamaks, and it is foreseen in ITER. During pellet injection, a movement of the ablated material towards the low- field side (or outward major radius direction) occurs because of the inhomogeneity of the magnetic field. Due to the complexity of the theoretical models, computer…
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UKAEA-CCFE-PR(23)042023
The High Field High Density Region (HFSFD) has been experimentally observed in both divertor and limiter tokamak devices. In order to numerically reproduced the HFSHD region in the limiter tokamak device J-TEXT, we first performed SOLPS-ITER simulations on the J-TEXT limiter tokamak with the activation of drifts, which is associated with the HFSHD …
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UKAEA-CCFE-CP(23)652022
The CHIMERA fusion technology test facility is currently under construction at the UK Atomic Energy Authority site in South Yorkshire, UK. With the completion of the engineering design, including the design of a component mock-up to be used in full system commissioning, this paper presents in detail the features and capabilities of the CHIMERA faci…
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