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UKAEA-CCFE-PR(25)3282025
Experiments and finite element modelling have been used to explore a method for miniaturising fibre push-out testing to the scale of thin ion irradiated layers. Correlation of interfacial surface area to debond stress has been identified for short fibres, and is related to a size effect following a Weibull distribution. Weibull analysis may be us…
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UKAEA-STEP-PR(25)312024
A strategy to prevent concentrated deposition of the exhaust power in a fusion device is to seed a localised ‘divertor’ region with impurity gas, which is chosen to radiate predominantly at the cooler electron temperatures associated with the plasma edge. If this impurity travels upstream to the main confined plasma, it can significantly impact…
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UKAEA-CCFE-PR(24)2602024
New RAFM steels, with intragranular VN precipitates for enhanced creep strength, were irradiated with 2MeV Fe+ ions at 600oC to explore MX-type precipitate response to extreme end-of-life conditions in breeder blanket components. Utilizing TEM, Analytical-STEM, and APT, the steels were characterized in the unirradiated and irradiated …
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UKAEA-CCFE-CP(25)062023
The EU-DEMO baseline design for the vacuum vessel (VV) currently provides for 48 openings – the so-called VV ports. These are foreseen to accommodate port plugs containing components, such as front ends for diagnostics and heating systems, first wall protection limiters and the first stages of the VV vacuum system. During the operation …
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UKAEA-CCFE-PR(24)2222023
During the operation of nuclear fusion reactors, plasma-facing components lining the reactor vessel are continually bombarded by plasma species. The penetration and subsequent trapping of these bombarding plasma ions has implications for component damage as well as in-vessel inventory. Accurately predicting the expected ion penetration depth pr…
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UKAEA-CCFE-PR(23)1612023
Severe plasma transients such as disruptions will impose high magnitude, short duration thermal loads on the plasma-facing first wall of the EU’s DEMOnstration tokamak. Repeated over DEMO’s lifetime, these transients may cumulatively alter the microstructure of first wall structural materials, degrading their performance. The effects of repeate…
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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(23)382022
The high ductile-to-brittle transition temperature (DBTT) of tungsten combined with its high hardness make machining incredibly difficult. These properties typically result in the poor-quality machined surfaces and short tool life. In this study, TiAlN coated carbide tools with different rake angles (8°, 10° and 12°) were tested in convention…
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UKAEA-RACE-PR(22)052022
During the EU DEMO Pre-Concept Design Phase, the remote maintenance team developed maintenance strategies and systems to meet the evolving plant maintenance requirements. These were constrained by the proposed tokamak architecture and the challenging environments but considered a range of port layouts and handling system designs. The design‑d…
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UKAEA-CCFE-PR(22)182022
A new method for the calculation of Shutdown Dose Rates (SDDR) has been developed, the Novel-1-Step (N1S) method. The new method retains the benefits of only requiring a single radiation transport calculation, as in the use of the direct-1-step (D1S) method, while removing the need for pre-calculations to determine dominant nuclides and time corr…
Showing 1 - 10 of 57 UKAEA Paper Results