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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-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)3112024
2D electron density profiles obtained from coherence imaging spectroscopy in different MAST-U divertor conditions are compared. The data includes variations of strike point position, core electron density, and heating power. The improved performance of the long-legged divertors results in a lower electron density and particle flux at the target com…
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UKAEA-CCFE-PR(24)2362024
Inconel 625 is a nickel-chromium based super alloy used in the construction of the vacuum vessel of the Joint European Torus (JET) experimental fusion device. It was selected for its mechanical properties at elevated temperature, being exposed to vacuum baking at >300°C and heat loads of typically 0.5 MW/m2 for recessed areas of t…
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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(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-CP(25)042023
2021 has culminated with the completion of the JET-ILW DTE2 experimental campaign. This contribution summarizes Ion Cyclotron Resonance Heating (ICRH) operations from system and physics point of view. Improvements to the (ICRH) system, to operation procedures and to real time RF power control were implemented to address specific constraints from…
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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…
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UKAEA-CCFE-PR(23)1822023
The reference ion cyclotron resonance frequency (ICRF) heating schemes for ITER deuterium-tritium (D-T) plasmas at the full magnetic field of 5.3 T are second harmonic heating of tritium and 3He minority heating. The wave-particle resonance location for these schemes coincide and are central at a wave frequency of 53 MHz at 5.3T [1]. Experiments ha…
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UKAEA-CCFE-PR(23)1802023
Showing 1 - 10 of 37 UKAEA Paper Results