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UKAEA-CCFE-PR(25)3052025
The MAST Upgrade Super-X divertor is typically seen to detach in steady state discharges. However, divertor re-attachment is observed to occur during fast transient heat loads. In this paper the effect of edge localised modes (ELMs) on the divertor are diagnosed on fast time scales with Thomson scattering and with a new ultrafast divertor spectrosc…
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UKAEA-CCFE-CP(25)092024
The successful development of fusion power will rely on the key technology of breeder blanket components. These components surround the fusion plasma, providing significant heat for power generation, and breeding the tritium fuel on which the plasma reaction depends. However, the technology for these components remains at a low technology readin…
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UKAEA-STEP-PR(25)242024
The UKAEA’s Spherical Tokamak for Energy Production (STEP) programme aims to demonstrate the ability of low aspect ratio tokamaks to generate net electricity from deuterium-tritium (DT) fusion. As STEP have selected REBCO coated conductor (CC) as the current carrier in most magnet systems, understanding how REBCO CC responds to the energetic p…
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UKAEA-CCFE-PR(24)2142024
In order to test the capability of the full electromagnetic DYON to predict the plasma initiation feasibility of individual discharges and thus the operating space in the device, a dedicated experimental database was built in MAST-U by scanning the prefilled gas pressure $p_0$ and the induced loop voltage $V_{loop}$ (3 failed breakdown discharge…
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UKAEA-STEP-PR(24)022024
Being a novel technology, estimating costs for fusion power plants comes with large uncertainties. Cost uncertainties in prototypes arise from various sources and reduce with programme maturity (including the selection of a site), technical and design maturity, maturity of the commercial strategy (e.g., make vs. buy decisions, partnering decisions)…
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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-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-PR(24)2592023
Two-micron thick erbium oxide tritium barrier coatings have been prepared by aerosol injection chemical vapor deposition and subsequently irradiated with 33 MeV Au 6+ ions at fluences up to 2.1×10 15 Au/m 2 at 550 o C. Scanning electron microscopy, X-ray diffraction and transmission electron microscopy were used to investigate the coating surf…
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UKAEA-STEP-CP(23)112023
The UKAEA’s Spherical Tokamak for Energy Production (STEP) program aims to demonstrate the ability of a low aspect ratio tokamak to generate net electricity from deuterium-tritium fusion. Specifically, its aim is to deliver a prototype fusion power plant, targeting 2040, and a path to the commercial viability of fusion, by engaging with and invig…
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UKAEA-STEP-PR(23)132023
Developments in fusion energy technology and the aspiration to build and run commercial fusion energy power plants has seen the commencement of numerous publicly and privately funded projects in recent years. Megaprojects, like fusion power plants, by their very nature are inherently complex and risky, therefore providing a robust cost estimate in …
Showing 1 - 10 of 35 UKAEA Paper Results