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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(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
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UKAEA-CCFE-PR(23)1442023
A dataset of baseline DT plasmas with peripheral HFS fuelling pellets has been produced on JET, in order to mimic the situtation in ITER. During the pellet ablation phase prompt particle losses due to pellet triggered ELM can be detected. Regarding pellet deposition, the data indicate that plasmoids drift velocity might be smaller than predicted…
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UKAEA-CCFE-PR(23)1152023
This article starts with a brief description of two new viewing systems with a light path which crosses the biological shield wall and are compatible with Deuterium-Tritium (D-T) operations in JET. However, it focuses on the optical modelling and engineering design of one of them which is a multiple camera system producing a wide angle view (WAV)…
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UKAEA-CCFE-PR(23)092023
Following from the paper describing the remote wide angle viewing system compatible with Deuterium-Tritium operations. This is the second article describing a second remote line of sight, this time focusing on the imaging of the divertor region in JET. It explains in detail the optical and engineering designs of constructing an optical relay which …
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UKAEA-CCFE-PR(23)1882022
In 2019, the JET-ILW was equipped with a Shattered Pellet Injector (SPI) system with a wide capability to allow studies on the efficacy of shattered pellets in reducing the electro-magnetic and the thermal loads during disruptions and the avoidance/suppression of the formation of runaway electrons. The fully commissioned system became operationa…
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UKAEA-CCFE-CP(23)402022
Shattered pellet injection (SPI), with research started in recent years, is the current concept for the ITER disruption mitigation system (DMS) to prevent disruption-related damage. Compared with impurity SPI, pure deuterium (D2) SPI could contribute to runaway electron (RE) avoidance in ITER via a strong dilution cooling before the thermal quen…
Showing 1 - 10 of 32 UKAEA Paper Results