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UKAEA-CCFE-PR(25)3232025
SOLPS-ITER simulations of the ITER baseline ($Q=10$) plasma boundary, with tungsten (W) targets and drift terms activated, exhibit a radially localised peak in the energy flux density entering the outer divertor, despite constant anomalous transport coefficients across the scrape-off layer (SOL). This peak occurs radially beyond the near-SOL energy…
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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)3092025
Neutral Beam Injection (NBI) is a powerful and very commonly used tool on machines used in the development of magnetically confined fusion power. Not all the neutral beam power is deposited within the plasma. This shinethrough power must be dealt with in the plasma vessel and any components irradiated by it must be protected against excessive he…
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UKAEA-RACE-PR(25)042025
The Vacuum Vessel Pressure Suppression System Remote Handling Equipment (VVPSS RHE) is being developed for remote maintenance of VVPSS components, including the Rupture Disc Assembly (RDA), Bleed Line Valve Assembly (BLVA), Support Trolley and relief lines within the Neutral Beam (NB) cell. It works in conjunction with the Neutral Beam Remote Ha…
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UKAEA-CCFE-PR(25)2722025
The development and distribution of microscopic shear strain have been investigated using high-resolution digital image correlation at the onset of plastic deformation in face-centred cubic CoCrFeNi high entropy al- loys with different grain sizes. Microscopic strain localisation increased with grain size as shown by the presence of planar slip …
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UKAEA-CCFE-PR(25)2652025
The development of discrete strain at the microstructural scale during the onset of plasticity is potentially linked to fatigue crack nucleation in engineering alloys. Hence, quantifying such discrete strain and its evolution is a pathway to understand the microstructural influence on fatigue crack nucleation and to develop crack initiation mode…
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UKAEA-CCFE-CP(25)092024
The successful development of fusion power will rely on the key technology of breeder blanket components. These components surround the fusion plasma, providing significant heat for power generation, and breeding the tritium fuel on which the plasma reaction depends. However, the technology for these components remains at a low technology readin…
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UKAEA-CCFE-PR(25)2762024
Creep-fatigue damage has been recognised as a critical failure mode for high-temperature structures. In fusion power reactors, plasma-facing components endure complex loading conditions, resulting in high thermomechanical stresses. These components, often made from 316L material, joined to ferritic-martensitic steels, face significant challenges…
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UKAEA-CCFE-CP(25)112023
Retention of tritium in structural materials of a fusion reactor is a concern for tritium accountancy, maintenance, and decommissioning. Plasma facing materials will be exposed to high temperatures, neutron damage and hydrogen isotopes. The damage caused by these conditions is a large area of exploration for fusion, with many questions still to…
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UKAEA-CCFE-PR(25)2852023
An overview of the preparation and implementation of the JET DTE2 Safety Case is presented. The Safety Case regime, developed by UKAEA for fusion applications to demonstrate compliance with relevant regulations, and its implementation on UKAEA sites is outlined. The hazard assessment process and details of the methodology applied to assess key J…
Showing 1 - 10 of 48 UKAEA Paper Results