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UKAEA-CCFE-PR(26)012025
Refractory High-Entropy Alloys (RHEAs) are promising candidates for structural materials in nuclear fusion reactors, where W-based alloys are currently leading. Fusion materials must withstand extreme conditions, including i) severe radiation damage from energetic neutrons, ii) embrittlement due to H and He ion implantati…
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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-RACE-PR(25)072025
Abstract: This study focuses on improving the control system of vehicle suspension, which is critical for optimizing driving dynamics and enhancing passenger comfort. Traditional passive suspension systems are limited in their ability to effectively mitigate road-induced vibrations, often resulting in compromised ride quality and vehicle handli…
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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)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-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)3672025
This study presents the validation of the finite element code ERMES 20.0, benchmarked against the well-established method-of-moments code TOPICA. The simulations focus on Ion Cyclotron Resonance Heating (ICRH) coupling for the JET A2 antennas. Validation is performed by comparing two key metrics: the scattering parameter matrix (S-matrix) and the …
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UKAEA-CCFE-PR(25)3662025
This study presents the validation of the frequency-domain finite element code ERMES 20.0, benchmarked against Finite Difference Time Domain (FDTD) solvers. The simulations focus on Ordinary–Extraordinary (O–X) mode conversion in the Electron Bernstein Wave (EBW) regime of the MAST Upgrade experiment. Validation is performed in terms of mode c…
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UKAEA-CCFE-PR(25)3592025
Edge Localized Modes (ELMs) pose a critical challenge to the safety and performance of plasma-facing components in tokamaks due to their periodic expulsion of heat and particles. This study investigates the behavior of various figures of merit for evaluating Resonant Magnetic Perturbations (RMPs) as a tool for achieving ELM control in the spherical…
Showing 11 - 20 of 438 UKAEA Paper Results