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UKAEA-CCFE-PR(25)3832025
Three tungsten Langmuir probes retrieved from the JET tokamak with the ITER-Like Wall(JET-ILW) from the bulk tungsten Tile 5 have been studied. Nano-indentation, microscopy, ionbeam analysis (IBA), and X-ray diffraction were used to assess changes in their mechanicalproperties, microstructure, and phase composition. Four region…
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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-CP(25)242025
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UKAEA-CCFE-PR(25)3802025
This Roadmap article addresses the critical and multifaceted challenge of plasma-facing component (PFC) damage caused by runaway electrons (REs) in tokamaks, a phenomenon that poses a significant threat to the viability and longevity of future fusion reactors such as ITER and DEMO. The dramatically increased RE production expected in future high-cu…
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UKAEA-CCFE-PR(25)3812025
This paper will highlight the driving objectives, structure and status of the DEMO Design Criteria for In-Vessel Components (DDC-IC), currently under development in EUROfusion. The goal is to complement the existing codes and standards and to provide a higher level of granularity in the structural integrity design qualification approaches specific …
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UKAEA-CCFE-PR(25)3792025
A robust disruption mitigation system (DMS) requires accurate characterization of key disruption timescales, one of the most notable being the thermal quench (TQ). Recent modeling of shattered pellet injection (SPI) into ITER plasmas, using JOREK and INDEX, suggests long TQ durations (6–10 ms) and slow cold front propagation due to the large p…
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UKAEA-CCFE-PR(25)3782024
We develop an atomic cluster expansion (ACE) interatomic potential for lithium that accurately models both the solid and liquid phase and the corresponding melting point. The predicted properties for both phases are in close agreement with density functional theory (DFT) and experimental data from literature. The potential is able to capture the…
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UKAEA-CCFE-PR(25)3752025
The National Spherical Torus Experiment (NSTX) at the Princeton Plasma Physics Laboratory in the United States, and the Mega Ampere Spherical Tokamak (MAST) at the United Kingdom Atomic Energy Authority in the United Kingdom, and their respective upgrades (NSTX-U and MAST-U) are two mega-amp class spherical tokamak fusion devices that have operated…
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UKAEA-CCFE-PR(25)3742025
Microwave diagnostics will be one of the few diagnostic techniques that can be operated in future fusion devices. In the past, they have contributed significantly to the understanding of the plasma dynamics, in particular electron cyclotron emission (ECE) and reflectometry. While these provide 1D measurements of plasma electron temperature and…
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UKAEA-CCFE-PR(25)3762024
Magnetic stochastic perturbations can strongly influence cross-field transport in high β tokamak plasmas. The impact of stochastic magnetic fields on electron heat transport in MAST/MAST-U is studied over a range in collisionality. Different formulae, based on the Rechester-Rosenbluth and the semi-empirical Rebut-Lallia-Walkins models, are used to…
Showing 111 - 120 of 2563 UKAEA Paper Results