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UKAEA-CCFE-CP(25)302025
Metal melting has been widely viewed as the most promising method for detritiating metallic waste, with its potential to release more tritium than other thermal methods. Furthermore, the homogenization of the metal post melting is expected to distribute tritium throughout the ingot, reduc…
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UKAEA-CCFE-PR(25)4022025
Multi-machine validation of full electromagnetic plasma initiation modelling with DYON was carried out by the joint modelling of the International Tokamak Physics Activity (ITPA) – Integrating Operating Scenario (IOS) group. The following devices were included in the experiment database: VEST (spherical torus, copper coils, Stainless steel wa…
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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-PR(25)3642025
The tokamak is a world-leading concept for produc- ing sustainable energy via magnetically-confined nuclear fusion. Identifying where to position the magnets within a tokamak, specifically the poloidal field (PF) coils, is a …
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UKAEA-CCFE-PR(25)3382025
Tungsten-based BCC superalloys utilising coherent intermetallic strengthening offer a route to improved high temperature
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UKAEA-CCFE-PR(25)3052025
The MAST Upgrade Super-X divertor is typically seen to detach in steady state discharges. However, divertor re-attachment is observed to occur during fast transient heat loads. In this paper the effect of edge localised modes (ELMs) on the divertor are diagnosed on fast time scales with Thomson scattering and with a new ultrafast divertor spectrosc…
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UKAEA-CCFE-PR(25)3692024
Plasma detachment in tokamaks is useful for reducing heat flux to the target. It involves interactions of the plasma with impurities and neutral particles, leading to significant losses of plasma power, momentum, and particles. Accurate mapping of plasma emissivity in the divertor and X-point region is essential for assessing the rel…
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UKAEA-CCFE-CP(25)092024
The successful development of fusion power will rely on the key technology of breeder blanket components. These components surround the fusion plasma, providing significant heat for power generation, and breeding the tritium fuel on which the plasma reaction depends. However, the technology for these components remains at a low technology readin…
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UKAEA-STEP-PR(25)242024
The UKAEA’s Spherical Tokamak for Energy Production (STEP) programme aims to demonstrate the ability of low aspect ratio tokamaks to generate net electricity from deuterium-tritium (DT) fusion. As STEP have selected REBCO coated conductor (CC) as the current carrier in most magnet systems, understanding how REBCO CC responds to the energetic p…
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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…
Showing 1 - 10 of 43 UKAEA Paper Results