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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)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(25)3782024
We develop an atomic cluster expansion (ACE) interatomic potential for lithium that accurately models both the solid and liquid phase and the corresponding melting point. The predicted properties for both phases are in close agreement with density functional theory (DFT) and experimental data from literature. The potential is able to capture the…
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UKAEA-CCFE-PR(25)3532024
The separation of lithium and the fractionation of the isotopes by solvent extraction was studied, using benzo-15-crown-5 as an extractant dissolved in a diluent of an ionic liquid and anisole. Equilibrium experiments were carried out in stirred vessels while continuous flow experiments were performed in small channels with 0.5 mm diameter. In the …
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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(25)3702023
14C is produced from the activation of N and O with high-energy neutrons. Due to its long half-life, high residence time in the environment and ease of assimilation into living matter, it is a major concern for the transportation of activated material and disposal of radioactive waste materials. This paper reports the discrepancy in the 14C product…
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UKAEA-CCFE-PR(25)3492023
Tungsten is one of the primary materials of choice for several commercial fusion power plant designs, in particular for divertor targets and 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, potentially distributing radioactive…
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UKAEA-CCFE-PR(24)2572023
Measuring temperatures between 100 and 150 million degrees, expected to be achieved in future fusion reactors, is a great challenge. Existing methods deliver ion temperature results with a delay from 5-10 minutes to several days after taking the measurements. A promising novel approach to real-time monitoring of deuterium-tritium plasma temperature…
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UKAEA-CCFE-PR(24)2552023
Helium-induced defect nucleation and accumulation in polycrystalline W and W-0.5wt.%ZrC (W-ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000 °С at the maximum damage level of 1 dpa. Radiation-induced dislocation loops were not observed in the current…
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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…
Showing 1 - 10 of 90 UKAEA Paper Results