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UKAEA-CCFE-PR(26)4062025
Neutron bombardment of high temperature superconducting (HTS) magnets may compromise the integrity of the magnetic confinement in future fusion reactors. The amount of damage produced by a single neutron can be predicted from the threshold displacement energies (TDE) of the constituent ions in the HTS materials, such as the Rare Earth Cuperates.…
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UKAEA-CCFE-PR(26)032025
Microstructural evolution–driven degradation governs material properties and is closely linked with defect behavior. Quantitatively characterizing defects and their evolution is essential for elucidating the underlying degradation mechanisms. To this end, the defects were introduced at room temperature using self-ion irradiation for damage lev…
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UKAEA-CCFE-PR(26)022025
Due to the extreme operating temperatures in nuclear fusion reactors, current materials exhibit a substantial mismatch in mechanical and thermal properties between the tungsten plasma-facing material and the CuCrZr heat sink cooling system. Therefore, a thermal barrier interlayer is required to guarantee continuous operation. In this work, (CrVW…
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UKAEA-CCFE-PR(26)012025
Refractory High-Entropy Alloys (RHEAs) are promising candidates for structural materials in nuclear fusion reactors, where W-based alloys are currently leading. Fusion materials must withstand extreme conditions, including i) severe radiation damage from energetic neutrons, ii) embrittlement due to H and He ion implantati…
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UKAEA-CCFE-PR(25)3992025
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 training data is obtained from 0 K density functional theory (DFT) and finite temperature ab initio molecular dynami…
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UKAEA-CCFE-PR(25)3772025
The vacancies and interstitials produced in high-energy collision cascades of irradiated tungsten can form prismatic dislocation loops with Burgers vectors 1⁄2⟨1 1 1⟩ and ⟨1 0 0⟩. The 1⁄2⟨1 1 1⟩ loops are very mobile, and their mobility is essential for the microstructure development of irradiated materials, It is a key parameter …
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UKAEA-CCFE-PR(25)3402025
Despite great efforts to study magnetic properties of 3d-transition metals from both fundamental and applied interest, there exists no modelling approach that would be able to describe magnetic and structural phase stability of all these elements on a unified formalism. In this work, we propose a qualitative improvement of the …
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UKAEA-CCFE-PR(25)3302025
A phase-field model is developed to simulate intergranular corrosion of ferritic/martensitic steels exposed to liquid lithium. The chromium concentration of the material is used to track the mass transport within the metal and liquid (corrosive) phase. The framework naturally captures intergranular corrosion by enhancing the diffusion of chromiu…
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UKAEA-CCFE-PR(25)3292025
Tungsten-based low-activation high-entropy alloys are possible candidates for next-generation fusion reactors due to their exceptional tolerance to irradiation, thermal loads, and stress. We develop an accurate and efficient machine-learned interatomic potential for the W–Ta–Cr–V system and use it in hybrid Monte Carlo mo…
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UKAEA-CCFE-PR(25)3272025
High-entropy alloys (HEAs) are being explored as potential candidates for radiation-tolerant materials, with some compositions exhibiting good resistance to defect cluster formation. One such system is WTaCrV, although only a single composition has been experimentally tested under ion irradiation, where it showed phase decomposition at low temperat…
Showing 1 - 10 of 94 UKAEA Paper Results