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UKAEA-CCFE-PR(26)4262025
The first results of studies of high-power (≥ 3 MW) H-mode discharges in double-null X-point-target (XPT) divertor configuration on MAST-U are presented. By combining the large strike point radius of the Super- X divertor with an additional X-point in the baffled outer divertor chambers, further exhaust benefits in strongly detached conditions…
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UKAEA-CCFE-PR(26)4232025
The MAST Upgrade Super-X divertor protects plasma-facing components from heat fluxes during steady-state operation and transient events. This paper examines heat loads from sawtooth events with energies of ΔWsawtooth ≈ 2–9 kJ in lower single null plasmas. The impact of deuterium and nitrogen gas pressures on mitigating these transients is inve…
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UKAEA-CCFE-PR(26)4222025
Dedicated experiments were conducted on Alfvénic instabilities in the ion sub-cyclotron frequency range excited by energetic beam ions in the MAST-Upgrade tokamak. Losses of the beam ions associated with plasma instabilities were measured with a scintillator-type fast ion lost detector (FILD), which provided a 2D image of the losses as functions o…
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UKAEA-CCFE-PR(25)4002025
The first measurements of energetic particle-driven ion cyclotron emission (ICE) in the Mega-Amp Spherical Tokamak Upgrade (MAST-U) have been obtained by adding a high sampling rate (250MHz) capability to one coil of the existing OMAHA array, oriented to measure fluctuations in the toroidal magnetic field component. All these measurements were carr…
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UKAEA-CCFE-PR(25)3862025
In high performance regimes short (sub ms) bursts of heat and particles from the core (edge localised modes, ELMs) happen cyclically increasing temporarily the heat flux by 2-3 orders of magnitude, and this can hardly be tolerated by large tokamaks. If ELMs happen when the target is detached the plasma temporarily reattaches and looses energy in th…
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UKAEA-CCFE-PR(25)3852025
The fusion research facility ITER is currently being assembled to demonstrate that fusion can be used for industrial energy production, while several other programmes across the world are also moving forward, such as EU-DEMO, CFETR, SPARK and STEP. The high engineering complexity of a tokamak makes it an extremely challenging device to optimise,…
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UKAEA-CCFE-CP(25)242025
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UKAEA-CCFE-CP(25)232025
The feasibility of laser-induced breakdown spectroscopy (LIBS) for measuring fuel retention was demonstrated for the first time in a tokamak operating with tritium using a remotely controlled in situ application in JET. In JET and future fusion reactors such as ITER and DEMO, thick co-deposited layers will be formed at the inner wall during exte…
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UKAEA-CCFE-PR(25)3552025
This study presents results from particle transport modelling for D/T ratio control experiments conducted during the JET DTE3 campaign. TRANSP interpretative and JETTO predictive simulations for D and T densities were performed and their results are discussed. Despite using simplified models based on Bohm-gyroBohm transport, the simulations inco…
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UKAEA-CCFE-PR(25)3462025
The JET Restart process is a critical phase in the operation of the Joint European Torus (JET), enabling the transition of JET plant from Shutdown to experimental plasma campaigns. This paper provides a comprehensive overview divided into its two main stages. The first stage, Integrated Commissioning, encompasses the activation and synchronizatio…
Showing 1 - 10 of 234 UKAEA Paper Results