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UKAEA-CCFE-PR(25)3152025
Neutral Beam Injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed Deuterium-Tritium Experimental campaign (DTE2) on the JET device. High NBI power was required for high fusion yield and alpha particle studies and to …
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UKAEA-CCFE-PR(25)3102025
An optical interlock protects the JET neutral beam ducts from damage if there is a fast pressure rise in the beam duct. The ability to trip during fault conditions and avoidance of false trips is limited by background light from the plasma and the additional light from radiation effects. A false trip occurred during the JET-DTE2 experimental cam…
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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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UKAEA-CCFE-PR(25)2822025
The Joint European Torus (JET) at Culham Campus completed its final deuterium tritium campaigns DTE2 and DTE3 in 2021 and 2023 respectively. These extremely successful campaigns provided record-breaking fusion power results and also allowed UKAEA to demonstrate running a tokamak with expected fusion energy fuels gaining experience in minimising …
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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.
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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-CP(25)122024
Neutron and gamma radiation is known to have deleterious effects on the properties of optical components. Optical fibres are especially vulnerable due to the long distances the light typically travels though them. In 2021 and 2023 JET has completed two D-T experimental campaigns where a significant amount of 14MeV neutrons were released.…
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UKAEA-CCFE-PR(25)2672024
The first generation of nuclear fusion reactors is expected to operate using a mixture of deuterium(D) and tritium(T) fuel. Controlling the D:T ratio is a promising option to control the fusion burn rate. The Joint European Torus (JET), as the only operational tokamak which can use tritium, is uniquely placed to test th…
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UKAEA-CCFE-CP(24)132024
An overview of the modelling approaches, validation methods and recent main results of analysis and modelling activities related to the plasma-wall interaction in JET-ILW experiments, including the recent H/D/T campaigns is presented in the paper. Code applications to JET-ILW experiments improve general erosion/migration/retention prediction cap…
Showing 1 - 10 of 223 UKAEA Paper Results