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UKAEA-CCFE-PR(25)3132025
This study aims to compare the effects of neutron and self-ion irradiation on the mechanical properties and microstructural evolution in W. Neutron irradiation at the HFR reactor to 1.67 dpa at 800 ◦C resulted in the formation of large Re and Os rich clusters and voids. The post-irradiation composition was measured using APT and verfified against…
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UKAEA-CCFE-PR(25)3082025
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UKAEA-CCFE-PR(25)3062025
Spinodal phase separation in SMART (Self-passivating Metal Alloys with Reduced Thermo-oxidation) materials based on binary W-Cr with alloying elements Y and Zr is systematically investigated by a combination of Density Functional Theory with Cluster Expansion Hamiltonian and large-scale Monte Carlo simulations with thermodynamic integration. Compar…
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UKAEA-CCFE-PR(26)4612024
Self-passivating W-11.4Cr-0.6Y (in wt.%) alloy is the plasma-facing armour material candidate in fusion power plants. In the present work, the as-sintered material, fabricated via ball milling and field-assisted sintering, was annealed at 1000℃ for varying durations to induce phase decomposition. This process leads to the transformation of the in…
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UKAEA-CCFE-PR(24)2672024
The self-passivating yttrium-containing WCr alloy has been developed and researched as a potential plasma-facing armour material for fusion power plants. This study explores the use of yttria (Y2O3) powders instead of yttrium elemental powders in the mechanical alloying process to assess their applicability in this material. Fabricated through f…
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UKAEA-CCFE-PR(24)2272024
Tungsten is one of the primary materials for several applications in commercial fusion power plant designs, in particular for divertor targets and the first wall. In maintenance conditions or during a loss of coolant accident, tungsten is expected to reach temperatures at which it readily volatilises as tungsten trioxide in contact with air, potent…
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UKAEA-CCFE-PR(26)4422023
We present a computational study employing Object Kinetic Monte Carlo simulations to investigate the behavior of D in self-irradiated Mo samples. Our simulations reveal that vacancy clusters contributing significantly to D diffusion, trapping, and desorption behavior. It is found that vacancy clusters play an important role in slowing the diffus…
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UKAEA-CCFE-PR(24)2492023
Short-range order (SRO) in multicomponent concentrated alloys affects their mechanical response. Hence, is paramount to understand how composition modifies the chemical ordering in the system to design materials with optimal properties. We present here a methodology to predict the SRO and thermodynamic properties in chemically complex systems an…
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UKAEA-CCFE-PR(24)2402023
In this study, we compare the formation of radiation induced defects in W and W-Re-Os alloys, exposed to an equivalent dose of self-ion and neutron irradiation. Transmutation reactions in the neutron irradiated material are simulated in the ion implanted materials by alloying with representative quantities of Re and Os (1.4 and 0.1 at.% respecti…
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UKAEA-CCFE-PR(24)062023
We describe the parameterization of a tungsten-hydrogen empirical potential designed for use with large-scale molecular dynamics simulations of highly irradiated tungsten containing hydrogen isotope atoms, and report test results. Particular attention has been paid to getting good elastic properties, including the relaxation volumes of small def…
Showing 11 - 20 of 40 UKAEA Paper Results