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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…
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       UKAEA-STEP-PR(25)272023
Electron Bernstein current drive (EBCD) systems are sensitive to plasma and launch conditions, and therefore require large parametric scans to optimise their design. One particular bottleneck in the simulation workflow is quasilinear modelling of current drive efficiency. Linear adjoint models are an attractive alternative, offering a ∼103× spee…
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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)2172023
Fusion energy offers the potential for a near limitless source of low-carbon energy and is oftenregarded as a solution for the world’s long-term energy needs. To realise such a scenario requiresthe design of high-performance fusion reactors capable of maintaining the extreme conditionsnecessary to enable fusion. Turbulence …
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       UKAEA-CCFE-PR(23)1832023
The development of improved designs for components which will be subject to high heat fluxes has been identified as a critical challenge for the realisation of commercial fusion power. This paper presents details of a facility which allows early verification of thermofluid and thermomechananical performance of prototype components and enables compa…
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       UKAEA-CCFE-PR(23)1732023
While modern nuclear decay data can provide many details of a given nuclides β-decay modes (branching ratios, decay heating etc), knowledge of the emitted β-energy spectrum is often not included. This limitation hampers the use of decay data in some analysis, such as β-spectrometry of irradiated material, prediction of β-decay Bremsstrahlung…
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       UKAEA-RACE-PR(23)052023
ITER In-Vessel Components (IVCs) will have limited lifetimes and need to be maintained and/or replaced during the operational life of ITER. IVCs are attached to the plant cooling water system via pipework to enable active cooling of the components during plasma operations. When maintenance is required, Remote Handling Systems (RHS) will be used …
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       UKAEA-CCFE-PR(23)1562023
Heat sinks have manifold applications, from micro-electronics to nuclear fusion reactors. Their performance expectations will continue to increase in line with the power consumption and miniaturisation of technology. Additive manufacturing enables the creation of novel, compact heat sinks with greater surface-to-volume ratios and geometrical comple…
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       UKAEA-CCFE-PR(23)1082023
This paper addresses two key issues regarding plasma exhaust in future fusion reactors. Firstly, using newly developed spectroscopic models to measure the divertor concentration of Ne and Ar, it is shown that the experimental detachment threshold on ASDEX Upgrade with Ar-only, an Ar+N mixture, and a Ne+N mixture scales as expected in comparison wit…
 
                Showing 11 - 20 of 56 UKAEA Paper Results