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UKAEA-STEP-PR(25)312024
A strategy to prevent concentrated deposition of the exhaust power in a fusion device is to seed a localised ‘divertor’ region with impurity gas, which is chosen to radiate predominantly at the cooler electron temperatures associated with the plasma edge. If this impurity travels upstream to the main confined plasma, it can significantly impact…
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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-PR(25)3252025
Maintaining an effective double-null configuration is expected to be challenging in reactor-scale tokamak devices. As divertor power-sharing is closely linked to the magnetic topology, even small variations can lead to fast power sharing fluctuations which exacerbate the already daunting exhaust challenge. While the static aspects of doubl…
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UKAEA-CCFE-PR(25)3242024
Calculation of stresses from high-resolution electron-backscatter diffraction (EBSD) maps has been a quite useful tool for understanding single- and polycrystal deformation. In this research, we used the weak form of a least-squares fit to the experimental measurements together with mechanical constraints in both two- and three-dimensional stress…
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UKAEA-CCFE-PR(25)3242024
Calculation of stresses from high-resolution electron-backscatter diffraction (EBSD) maps has been a quite useful tool for understanding single- and polycrystal deformation. In this research, we used the weak form of a least-squares fit to the experimental measurements together with mechanical constraints in both two- and three-dimensional stress…
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UKAEA-CCFE-PR(25)3232025
SOLPS-ITER simulations of the ITER baseline ($Q=10$) plasma boundary, with tungsten (W) targets and drift terms activated, exhibit a radially localised peak in the energy flux density entering the outer divertor, despite constant anomalous transport coefficients across the scrape-off layer (SOL). This peak occurs radially beyond the near-SOL energy…
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UKAEA-CCFE-PR(25)3222025
The development of quantitative models for understanding physical properties of alloys requires a proper treatment of magnetic interactions, which is of paramount importance for the microstructural stability, especially in steels and high-entropy alloys containing magnetic elements. These magnetic interactions also control the defects behavior w…
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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)3192025
Fe–Cr binary alloys serve as simplified model systems to study irradiation damage relevant to fusion structural materials. Here, Fe-3%Cr and Fe-5%Cr samples were irradiated with 4 MeV Fe ions with a dose rate of 4 × 10⁻⁵ dpa/s across a linear thermal gradient (120°C–480°C) in a single experiment, enabling direct comparison of temperatu…
Showing 201 - 210 of 2581 UKAEA Paper Results