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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…
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UKAEA-CCFE-PR(25)2672024
The first generation of nuclear fusion reactors is expected to operate using a mixture of deuterium(D) and tritium(T) fuel. Controlling the D:T ratio is a promising option to control the fusion burn rate. The Joint European Torus (JET), as the only operational tokamak which can use tritium, is uniquely placed to test th…
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UKAEA-CCFE-PR(24)2662024
A new type of resonant magnetic perturbation (RMP), generated by helical coils, is proposed for controlling the edge localized mode (ELM) in H-mode tokamak plasmas. The helical coil optimization utilizes the MARS-F code (Liu et al 2000 Phys. Plasmas 7 3681) computed linear resistive fluid response of the plasma to the applied RMP field. The opti…
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UKAEA-CCFE-PR(24)2612024
The fusion reaction between deuterium and tritium, D(T,n)4He is the main source of energy in future thermonuclear reactors. Alpha-particles (4He-ions) born with an average energy of 3.5MeV transferring energy to the thermal plasma during their slowing down, they should provide the self-sustained D-T
Showing 1 - 10 of 37 UKAEA Paper Results