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UKAEA-CCFE-PR(26)4272025
Reduced activation ferritic-martensitic (RAFM) steels are a recent class of radiation-resistant steels designed for the structural components of power-producing fusion reactors. In this work an advanced (A)RAFM steel has been developed with superior radiation hardening resistance with respect to the EUROFER-97 upon which it was based. 4D-STEM (s…
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UKAEA-CCFE-PR(26)4232025
The MAST Upgrade Super-X divertor protects plasma-facing components from heat fluxes during steady-state operation and transient events. This paper examines heat loads from sawtooth events with energies of ΔWsawtooth ≈ 2–9 kJ in lower single null plasmas. The impact of deuterium and nitrogen gas pressures on mitigating these transients is inve…
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UKAEA-CCFE-PR(26)4212025
The competing requirements of fusion breeder blankets and the high dimensionality of their design space necessitate a systematic treatment to map the variations in performance against given objective metrics and to understand the operational envelope. In this endeavour, a digital engineering pipeline for design evaluation and optimisation has be…
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UKAEA-CCFE-CP(26)362025
Predicting with high accuracy (low uncertainty) the performance of tritium breeding systems is a must for design engineering of future fusion devices. Current modelling relies on scant experimental data and is known to have uncertainties that if realised in a real system would p…
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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…
Showing 1 - 10 of 54 UKAEA Paper Results