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UKAEA-CCFE-PR(26)4302026
In the paper we present validated integrated modelling of JET experiments in which fusion performance is driven by reactions between fast ions and intrinsically present metal wall impurities. A steady-state L-mode plasma with dominant proton-beryllium fusion and neutron yields of up to ≈ 6 x 1013 s-1 is developed in He and D…
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UKAEA-CCFE-PR(26)4372025
Vanadium-based alloys such as V-4Cr-4Ti are of interest as candidates for low activation structural materials for advanced nuclear reactors. One of the major challenges of vanadium-based alloys is their thermal stability and improving their mechanical properties at higher temperature ranges (> 600 °C). This work explores re…
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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-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)3272025
High-entropy alloys (HEAs) are being explored as potential candidates for radiation-tolerant materials, with some compositions exhibiting good resistance to defect cluster formation. One such system is WTaCrV, although only a single composition has been experimentally tested under ion irradiation, where it showed phase decomposition at low temperat…
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2025
This work examines the separatrix and SOL characteristics in three scenarios on JET: the Quasi-Continuous Exhaust (QCE) regime, the core-edge-SOL integrated ITER Baseline scenario, and the X-point Radiator (XPR) regime. All three scenarios are potentially compatible with reactor operations, as they aim to provide power exhaust solutions through dif…
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UKAEA-CCFE-CP(25)212024
Tritium inventory build-up is a safety issue for next step devices. JET brings a unique contribution on fuel retention and recovery in a metallic device, as it has operated both in deuterium (D) and deuterium-tritium (DT) plasmas. This paper will provide an overview of results from JET in this fi…
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UKAEA-CCFE-PR(25)3532024
The separation of lithium and the fractionation of the isotopes by solvent extraction was studied, using benzo-15-crown-5 as an extractant dissolved in a diluent of an ionic liquid and anisole. Equilibrium experiments were carried out in stirred vessels while continuous flow experiments were performed in small channels with 0.5 mm diameter. In the …
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UKAEA-CCFE-CP(25)142024
The typical pulse on the JET tokamak is ~10s during the main phase of the discharge, however long discharge operation (>30s) is possible with sufficient preparation and care. During the last period of JET operation in 2023 long pulses in deuterium plasmas were developed to assess the sustainment of the plasma performance over current resistive t…
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UKAEA-CCFE-PR(25)3202024
The development of a high current baseline scenario (I_p = 3.5MA, q95 ~3.0, beta_N < 2) in deuterium (D), tritium (T) and deuterium-tritium (D-T) for high DT fusion performance at JET with Be/W wall is described. We show that a suitable scenario capable of delivering up to 10 MW of fusion power, depending on the auxiliary heating power avail…
Showing 1 - 10 of 40 UKAEA Paper Results