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UKAEA-STEP-PR(25)232023
The purpose of this work was to establish an approach to drive the development, at pace, of a commercially relevant Spherical Tokamak Concept. Building on the table of parameters and idealised geometry generated from the work of S. Muldrew et al [1], applying core principles, tools, and approaches. The generation and utilisation of a reflective …
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UKAEA-CCFE-CP(24)142023
Accurate quantification of the power loss channels and overall power balance of the plasma is essential for the safe operation of current and future fusion devices. The relative magnitudes of core radiation, SOL radiation and divertor target heat loading are determining factors in both PFC design and plasma scenario design in the successful real…
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UKAEA-CCFE-PR(24)2582023
The integration of good core and edge/pedestal confinement with strong dissipation of heat and particles in the divertors is a significant challenge for the development of fusion energy. Alternative divertor configurations offer potential advantages by broadening the operational space where a device can operate with detached divertors and acce…
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UKAEA-CCFE-PR(24)2532023
By utilising Field Programmable Gate Arrays (FPGA), in a configuration similar to that of the Mirror Langmuir Probe, it is possible to bias a single probe at 3 precise voltages in sequence. These voltages can be dynamically adjusted in real-time based on the measured plasma temperature to ensure the transition region is always sampled. First result…
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UKAEA-CCFE-PR(24)2452023
2021 JET experimental campaign has produced high stationary fusion power with 50%D 50%T discharges, operated with the ITER-relevant conditions i.e. operation with the baseline or hybrid scenario in the full metallic wall. It has provided a unique opportunity to assess the DT fusion power prediction capability before ITER DT experiments. This pap…
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UKAEA-CCFE-PR(24)2192023
Heat transfer is a key consideration in the development of tritium breeder blankets for future fusion reactors. For solid tritium breeder materials there is a a fine balance to be struck between high levels of porosity to encourage tritium release and minimising it to maintain the thermal and mechanical properties. Therefore, in this work we emp…
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UKAEA-CCFE-CP(24)042023
A new bolometer camera was installed in the upper divertor chamber of MAST Upgrade between the MU01 and MU02 physics campaigns. Sharing viewing geometry with the existing lower divertor horizontal bolometer camera, this enables direct comparison of the radiated power in the two divert…
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UKAEA-CCFE-CP(24)032023
Measurements are presented, alongside corresponding interpretative SOLPS-ITER simulations, of the first MAST-U experiments comparing ohmically heated L-mode fuelling scans in Conventional divertor (CD) and Super-X divertor (SXD) configurations. In experiment, at comparable outer mid-plane separatrix electron density, ne,sep,OMP, the maximum lower o…
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UKAEA-CCFE-PR(23)1912023
ITER is of key importance in the European fusion roadmap as it aims to prove the scientific and technological feasibility of fusion as a future energy source. The EUROfusion consortium of labs is contributing to the preparation of ITER scientific exploitation and operation and aspires to exploit ITER outcomes in view of DEMO. The paper provides …
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UKAEA-CCFE-PR(23)1892023
The separation of hydrogen isotopes is a vital step in preparing tritium and deuterium fuels for future fusion energy plants. This represents a fundamental challenge to fusion energy since the separation process must be able to handle high throughputs of hydrogen isotopes with a low tritium inventory, as tritium is highly radioactive and hazardo…
Showing 61 - 70 of 353 UKAEA Paper Results