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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)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)3772025
The vacancies and interstitials produced in high-energy collision cascades of irradiated tungsten can form prismatic dislocation loops with Burgers vectors 1⁄2⟨1 1 1⟩ and ⟨1 0 0⟩. The 1⁄2⟨1 1 1⟩ loops are very mobile, and their mobility is essential for the microstructure development of irradiated materials, It is a key parameter …
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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)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)3622025
In this work we present the assessment framework for magnetic equilibrium controllers on MAST-U spherical tokamak. Such controllers are essential for MAST-U since exhaust physics and core-edge integration studies require advanced divertor plasma configurations. The developed framework is based on the TokSys suite of plasma control codes, which was …
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UKAEA-CCFE-PR(25)3372025
Most research reactors (RRs) in Europe are over 60 years old, and there are only limited efforts underway (e.g., PALLAS and JHR projects) to partially replace this aging infrastructure. Continued safe operation (CSO) of these reactors is crucial to sustaining the EU’s leadership in nuclear materials development and qualification for advanced r…
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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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2025
This paper presents a comprehensive user study aimed as assessing and differentiating operator expertise within bilateral teleoperation systems. The primary objective is to identify key performance metrics that effectively distinguish novice from expert users. Unlike prior approaches that focus primarily on psychological evaluations, this study emp…
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UKAEA-CCFE-PR(25)2962025
In the EU DEMO reactor, the Water-Cooled Lithium-Lead Tritium Extraction and Removal system (WCLL TER) is dedicated to transporting tritium-rich PbLi from the Breeding Blanket to the Tritium Extraction Unit and then back to it, after tritium is extracted and routed to the fuel cycle. In addition to circulating PbLi and extracting tritium, the TE…
Showing 11 - 20 of 353 UKAEA Paper Results