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UKAEA-CCFE-PR(24)2162023
The first pedestal stability analysis on the new MAST Upgrade (MASTU) spherical tokamak H-mode plasma is presented. Our results indicate that MAST-U pedestals are close to the low toroidal mode number (n) peeling branch of the peelingballooning instability, in contrast with MAST H-mode pedestals which were deeply in the high-n ballooning branch. Th…
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UKAEA-STEP-PR(23)162023
During development of the UKAEA’S Spherical Tokamak for Energy Production (STEP), assessment of manufacturing strategies for the inboard shield identified several gaps in knowledge. Limits arose from the modularization of this component, geometric constraints of tungsten ceramic forming, joining with low-activation interlayers and dissimilar j…
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UKAEA-STEP-PR(23)152023
Tritium self-sufficiency is one of the fundamental challenges for deuterium-tritium nuclear fusion reactors. The combination of key high temperature radiation shielding materials that possess dense, high neutron absorption cross-section, and moderation properties, and tritium breeding materials could involve interesting design spaces for the centra…
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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-CCFE-CP(23)632023
The real time plasma control system for the MAST Upgrade tokamak has been substantially redeveloped from its original MAST incarnation with a new architecture that aims to manage complexity whilst maximising flexibility. It provides modular layers of functionality and supports the implementation of virtual actuators to aggregate, arbitrate and rout…
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UKAEA-CCFE-PR(23)1192023
MAST Upgrade has just begun its second physics campaign. The set of magnetic probes used to diagnose the magnetic field and currents on MAST Upgrade are described, and their calibration procedures outlined including calculation of uncertainties. The arrays of installed instability diagnostics are described and the detection and diagnosis of a speci…
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UKAEA-CCFE-CP(23)022023
Understanding the plasma parameters that affect the scrape off layer (SOL) width is a key issue for future tokamaks as the power entering the SOL (of order 100 MW [1] in ITER) and the SOL width (of order millimetres [2]) determine the heat flux to the divertor surfaces. The Eich scaling [2] can be used to characterise the divertor heat flux prof…
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UKAEA-CCFE-CP(23)382022
The high ductile-to-brittle transition temperature (DBTT) of tungsten combined with its high hardness make machining incredibly difficult. These properties typically result in the poor-quality machined surfaces and short tool life. In this study, TiAlN coated carbide tools with different rake angles (8°, 10° and 12°) were tested in convention…
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UKAEA-STEP-PR(23)032022
Commercial fusion power plants will require strong magnetic fields that can only be achieved using state-of-the-art high temperature superconductors in the form of REBCO coated conductors. In operation in a fusion machine, the magnet windings will be exposed to fast neutrons that are known to adversely affect the superconducting properties of RE…
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UKAEA-CCFE-PR(22)872022
The neutral ionisation model proposed by R J Groebner et al. (Phys Plasmas 9 2134 (2002)) to determine the plasma density profile in the H-mode pedestal, extended to include charge exchange processes in the pedestal stimulated by the ideas of Mahdavi et al. ((Phys Plasmas 10 3984 (2003)). The model is then teste…
Showing 1 - 10 of 123 UKAEA Paper Results