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UKAEA-CCFE-PR(26)4832026
Predicting three-dimensional thermal loads during tokamak disruptions is essential for ITER yet remains weakly developed. We present a physics-based workflow that couples MHD simulations of vertical displacement events with field line tracing on a realistic 3D first wall model and a transient wall thermal response. The approach is validated agai…
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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)4732024
Components on the inner wall of fusion reactors are exposed to extremely high heat loads, and significant care must be taken to minimise the damage to these components during operation. UFOs, also known as Transient Impurity Events (TIEs), are small particles of dust within the tokamak vessel which can lead to plasma disruptions. These can cause se…
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UKAEA-CCFE-PR(26)4532024
Experimental campaigns at the Joint European Torus with an ITER-like Be/W wall (JET-ILW) with pure deuterium (D), tritium (T) and Deuterium-Tritium (DT) were a unique opportunity to explore various aspects related to the ITER operation. It should also be emphasized that the JET campaign at the end of 2021 included the first tokamak experiments u…
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UKAEA-CCFE-PR(25)4042024
JET is the only tokamak capable of Deuterium-Tritium (D-T) operations. The first D-T operations were in the 1990s and again in 2004. In 2020/2021 JET operated a much larger D-T campaign aimed at sustained high fusion power requiring a much higher tritium throughput. This paper presents an overview of the recent Tritium Injections into the JET To…
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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(26)4412023
The pre-thermal quench (pre-TQ) dynamics of a pure deuterium (D2) shattered pellet injection (SPI) into a 3 MA/7MJ JET H-mode plasma is studied via 3D non-linear MHD modelling with the JOREK code. The interpretative modelling captures the overall evolution of the measured density and radiated power. The simulations also identify the importance of t…
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UKAEA-CCFE-PR(25)2892023
This paper reports the first experiment carried out in deuterium–tritium addressing the integration of a radiative divertor for heat-load control with good confinement. Neon seeding was carried out for the first time in a D–T plasma as part of the second D–T campaign of JET with its Be/W wall environment. The technical difficulties linked to …
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UKAEA-CCFE-PR(24)2472023
The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challeng…
Showing 1 - 10 of 34 UKAEA Paper Results