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UKAEA-CCFE-PR(25)3032025
Screening of high-Z (W) impurities from the confined plasma by the temperature gradient at the plasma periphery of fusion-grade H-mode plasmas was demonstrated for the first time in JET with the Be/W wall [Field A R et al, Nucl. Fusion 63(2023) 016028]. Through careful optimisation of the hybrid-scenario, deuterium plasmas with sufficient heating p…
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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-PR(26)4652024
Deuterium retention was measured in beryllium samples from the JET ITER-like wall limiter tiles that were in the JET vessel for one and three campaigns (in vessel during 2015-2016 and 2011-2016, respectively), using thermal desorption spectroscopy, ion beam analysis and secondary ion mass spectrometry. It was found that overall retention increas…
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UKAEA-CCFE-PR(26)4542024
A fast neutral lithium beam is used at JET for more than 30 years to measure profiles of electron density in the pedestal and scrape off layer. The diagnostic was not designed for tritium operation. In this paper, we describe the modifications which were required to allow operation in tritium (T) and deuterium-tritium (D-T ) fuelled pulses at JE…
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UKAEA-CCFE-PR(26)4512024
An understanding of the behaviour of the D or He fuel used in tokamak discharges is essential in analyses such as modelling edge and divertor transport and the erosion of the vessel walls. However, poor agreement is found between measurements made on the JET tokamak and collisional-radiative models used …
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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-PR(25)3572024
Profiles of power deposition on the first wall of the Joint European Torus (JET) tokamak experiment are fitted by tracing an analytic representation for the distribution of power from midplane along lines of magnetic field. The technique is used to help design plasma facing components (PFCs) in reactor-scale magnetic confinement devices, hence un…
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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-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-CP(25)132024
The end of tokamak operations at the Joint European Torus in December 2023 brought to a close the experimental life of an extraordinary fusion research facility.
Showing 21 - 30 of 510 UKAEA Paper Results