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UKAEA-CCFE-PR(24)2322024
The JET-ILW pure Tritium and Deuterium-Tritium (DTE2) experimental campaigns took place in 2021-2022. Tritium (T) and Deuterium-Tritium (D-T) operations present challenges not encountered in present day tokamaks [1]. This contribution focuses on Ion Cyclotron Resonance Heating (ICRH) operations in tritium and deuterium-tritium plasmas, starting …
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UKAEA-CCFE-PR(24)2282024
This work presents a system upgrade of the High Resolution Thomson Scattering (HRTS) diagnostic on JET that allows it to measure low temperature (1 to 500 eV) plasma pre- and post-Thermal quench (TQ), which would help to further the understanding of the physics in SPI experiments. The upgrade was done by connecting optic fibres from the original…
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UKAEA-CCFE-PR(26)4432023
This work presents the results following the first irradiation of ITER materials samples in a tokamak D–T plasma environment operating at significant fusion power. The materials exposed to this nuclear environment at the Joint European Torus include representative ITER samples from various components such as poloidal field (PF) coil jacket…
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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-CP(26)412023
In 2021 JET exploited its unique capabilities to operate with T and D–T fuel with an ITER-like Be/W wall (JET-ILW). This second major JET D–T campaign (DTE2), after DTE1 in 1997, represented the culmination of a series of JET enhancements—new fusion diagnostics, new T injection capabilities, refurbishment of the T plant, increased auxiliary h…
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UKAEA-CCFE-CP(25)292023
INTRODUCTION Future generation tokamaks, including ITER, will strive for better confinement, which means a higher fusion plasma current to achieve a good Fusion Efficiency Factor value greater than 10 [1]. One of the major threats with this scenario is a potential for increased damage of first wall components due to unmitig…
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UKAEA-CCFE-CP(25)262023
Model-based plasma scenario development lies at the heart of the design and operation of future fusion powerplants. Including gyrokinetic turbulence in integrated models is essential for delivering a successful roadmap towards operation of ITER and the design of DEMO-class devices. Given the highly iterative nature of integrated models, fast mac…
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UKAEA-CCFE-CP(25)152023
Reduced plasma models play a pivotal role in swiftly interpreting experiments, exploring different reactor design points, and providing consistency checks for high-fidelity simulations. This presentation focuses on reduced models for plasma detachment onset and transient reattachment timescales, assessing their validity across ASDEX Upgrade, JET…
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UKAEA-CCFE-CP(25)082023
JET, the world’s largest tokamak with unique ITER-like Be/W wall and tritium handling capability had completed its second Deuterium-Tritium (DT) campaign in 2021 following a decade of preparatory experiments, technical rehearsals and training, dedicated enhancements. Operation with tritium raises significant technical, safety and scientific ch…
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UKAEA-CCFE-PR(25)2912023
We compare the structure of electron temperature gradient (ETG) driven turbulence in the pedestals of two JET ITER-like-wall (ILW) type I ELMy H-mode discharges operating with similar experimental inputs but at different levels of gas fuelling. By artificially removing the toroidal drifts from our GENE gyrokinetic simulations and subsequently an…
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