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UKAEA-CCFE-PR(26)4242025
The generation and accumulation of dust in future nuclear fusion reactors pose challenges related to safety, waste management and environmental impact. Dust, flakes and droplets form because of plasma-facing component erosion, with highly tritiated and activated materials accumulating in-vessel and during decommissioning activities. Estimations for…
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UKAEA-CCFE-CP(25)302025
Metal melting has been widely viewed as the most promising method for detritiating metallic waste, with its potential to release more tritium than other thermal methods. Furthermore, the homogenization of the metal post melting is expected to distribute tritium throughout the ingot, reduc…
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UKAEA-CCFE-PR(26)4092024
We recast the Howie-Whelan equations for generating simulated transmission electron microscope (TEM) images, replacing the dependence on local atomic displacements with atomic positions only. This allows very rapid computation of simulated TEM images for arbitrarily complex atomistic configurations of lattice defects and dislocations in the dyna…
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UKAEA-CCFE-PR(24)2182024
Mixed convection of an electrically conductive fluid in a square duct with imposed transverse magnetic field is studied using Large Eddy Simulation (LES) paradigms. The duct walls are electrically conductive, with the wall conductivity parameter cw ranging from 0 to 0.5. The Reynolds number is Re = 5602 and the Prandtl number is Pr = 0.0238. The fo…
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UKAEA-CCFE-PR(25)2902023
The augmentation of mechanical properties of reduced activation ferritic martensitic steels through the introduction of creep resistant nano-oxide particles produces a class of oxide dispersion strengthened steels, which have attracted significant interest as candidates for first wall supporting structural materials in future nuclear fusion reac…
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UKAEA-CCFE-CP(24)102023
The successful realisation of energy production through the fusion of deuterium and tritium will necessarily lead to the generation of waste contaminated with tritium. Not only will some of the tritium fuel permeate into components of fusion reactors and their wider fuel cycle, but tritium will also be generated directly in materials exposed to the…
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UKAEA-CCFE-PR(23)132023
Following the first Deuterium-Tritium Experiment (DTE1) at UKAEA, modifications were investigated to the Joint European Torus’ (JET) gas introduction systems to increase the gas feed capabilities of the JET facility to better support future campaigns. The gas introduction systems comprise the gas introduction and gas distribution system (GI/GD)…
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UKAEA-CCFE-CP(24)012022
Investigations were undertaken into the thermal treatment of beryllium and tungsten to see if these materials can be detritiated in the Material Detritiation Facility (MDF) at UKAEA, allowing for the declassification of intermediate level waste (ILW) to low level waste (LLW). When heated in oxygen, both tungsten and beryllium readily oxidise, wi…
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UKAEA-CCFE-CP(23)592022
Investigations were undertaken into the thermal treatment of beryllium and tungsten to see if these materials can be detritiated in the Material Detritiation Facility (MDF) at UKAEA, allowing for the declassification of intermediate level waste (ILW) to low level waste (LLW). When heated in oxygen, both tungsten and beryllium readily oxidise, wi…
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UKAEA-CCFE-CP(25)052021
Commercial generation of electricity via fusion technology remains one of the promising alternatives to help meet the challenging targets to decarbonize the global energy system. Fusion technology can play a significant role as part of the long-term switch from carbon-based fuels to electricity, due to superior energy output per energy generation a…
Showing 1 - 10 of 22 UKAEA Paper Results