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UKAEA-CCFE-CP(25)242025
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UKAEA-CCFE-PR(25)3832025
Three tungsten Langmuir probes retrieved from the JET tokamak with the ITER-Like Wall(JET-ILW) from the bulk tungsten Tile 5 have been studied. Nano-indentation, microscopy, ionbeam analysis (IBA), and X-ray diffraction were used to assess changes in their mechanicalproperties, microstructure, and phase composition. Four region…
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UKAEA-CCFE-CP(25)232025
The feasibility of laser-induced breakdown spectroscopy (LIBS) for measuring fuel retention was demonstrated for the first time in a tokamak operating with tritium using a remotely controlled in situ application in JET. In JET and future fusion reactors such as ITER and DEMO, thick co-deposited layers will be formed at the inner wall during exte…
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UKAEA-CCFE-PR(25)3282025
Experiments and finite element modelling have been used to explore a method for miniaturising fibre push-out testing to the scale of thin ion irradiated layers. Correlation of interfacial surface area to debond stress has been identified for short fibres, and is related to a size effect following a Weibull distribution. Weibull analysis may be us…
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UKAEA-CCFE-PR(25)3682024
This research utilizes established cyclic deformation models to simulate the Bauschinger effect observed in copper monocrystal cantilever experiments during the initial bending and straightening phases. Crystal plasticity finite element simulations employing Armstrong-Frederick, Orowan-Sleeswyk, and various other backstress models have failed to…
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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(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…
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UKAEA-CCFE-CP(25)292023
INTRODUCTION Future generation tokamaks, including ITER, will strive for better confinement, which means a higher fusion plasma current to achieve a good Fusion Efficiency Factor value greater than 10 [1]. One of the major threats with this scenario is a potential for increased damage of first wall components due to unmitig…
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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(24)092023
The JET ITER-like Wall (ILW) divertor mostly consists of CFC tiles coated with a thick tungsten (W) layer over a molybdenum (Mo) interlayer. Poloidal sets of tiles are additionally coated with ~3 microns of Mo and ~4 microns of W to act as markers to measure the erosion/deposition during ILW campaigns. A few of the marker tiles only have the Mo …
Showing 1 - 10 of 37 UKAEA Paper Results