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UKAEA-CCFE-PR(25)3432023
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UKAEA-CCFE-CP(25)072023
The EU-DEMO first wall protection strategy relies on limiter components to face both normal and off-normal plasma transient events. The heat loads during these events are likely to damage the breeding blanket first wall otherwise. Since tungsten is the preferred plasma-facing material for EU-DEMO, the plasma-facing component design of the limite…
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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-CP(25)032022
The UK Spherical Tokamak for Energy Production (STEP) program is currently progressing the conceptual engineering design of a Spherical Tokamak-based fusion reactor. The program includes a project concerned with design of the reactor breeding blanket. The objective of this work was to develop a low fidelity, integrated simulation approach to sup…
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UKAEA-CCFE-PR(25)2902023
The augmentation of mechanical properties of reduced activation ferritic martensitic steels through the introduction of creep resistant nano-oxide particles produces a class of oxide dispersion strengthened steels, which have attracted significant interest as candidates for first wall supporting structural materials in future nuclear fusion reac…
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UKAEA-CCFE-PR(25)2842023
Nuclear fusion is a potential source of electricity which can address the environmental problems posed by fossil fuels. Eurofer97 steel is a primary structural material for breeding blanket and divertorcomponents in fusion Tokamaks.. Assembling and maintaining the structural integrity of these in-vessel components requires remote joint technique…
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UKAEA-CCFE-CP(25)022022
Within the EU-DEMO first wall protection framework, work on limiter’s plasma-facing component design has started under plasma disruptive events (Richiusa et al., 2022). Starting from the rationale behind the TARTIFL&TTE software (Richiusa et al., 2022), this companion paper describes the progress on the engineering modelling of the plasma-facing …
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UKAEA-CCFE-PR(25)2752021
Several fusion power concepts propose the use of liquid lithium as the primary coolant and tritium breeder. Conventional Heat Exchangers (HEX) use water. In order to avoid tritium permeation into water, a molten salt can be used as secondary coolant, with water as the tertiary system. Nevertheless, the design of the HEX to transfer the energy fr…
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UKAEA-CCFE-PR(25)2662024
This paper reports on a FEM-based computational methodology to assess dynamic amplification factors (DAF) of a divertor cassette, under electromagnetic (EM) impact loads caused by a plasma disruption event. The investigation concerns a typical divertor cassette body (CB) of the European DEMO reactor (baselin…
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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 179 UKAEA Paper Results