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UKAEA-CCFE-PR(24)2312024
The status of research and development on vanadium alloys and on their application as a structural material in the breeder blanket of a fusion power plant are reviewed. Emphasis has been placed on irradiation experiments and the effects of neutron and ion irradiation on the microstructure of the current reference alloy, V-4Cr-4Ti. The effects of a …
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UKAEA-CCFE-PR(26)4462023
This work investigated the impact of electron beam (EB) welding, and in particular varying the transverse speed of the electron beam (i.e. 1200-2200 mm/min), on the resultant microstructure of PM2000 ODS steel, using analytical electron microscopy and microhardness. The resultant range of heat inputs during welding explored in this study (72-39 J/m…
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UKAEA-CCFE-PR(26)4442023
Abnormal (deviating from target) variations in the plasma current Ip and vertical position Z constitute common cross-shot/device elements of a disruption, a phenomenon that is to be avoided (or ultimately mitigated) in future reactor-relevant tokamaks. Those abnormalities constitute important instances within disruptive chain of events (e.g. spi…
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UKAEA-CCFE-PR(26)4392023
Disruption prediction and avoidance is a critical need for next-step tokamaks such as ITER. Disruption Event Characterization and Forecasting (DECAF) research fully automates analysis of tokamak data to determine chains of events that lead to disruptions and to forecast their evolution allowing sufficient time for mitigation or complete avoidance o…
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UKAEA-CCFE-PR(23)1592023
Fusion power output from spherical tokamaks would benefit from increased confined plasma density, but there exists a limit on the density before confinement is lost and the plasma current is disrupted. This density limit has long been characterized by a simple, global Greenwald limit proportional to the plasma current and inversely proportional …
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UKAEA-CCFE-PR(22)552022
The MAST-U fusion plasma research device, the upgrade to the Mega Amp Spherical Tokamak, has recently completed its first campaign of physics operation. MAST-U operated with Ohmic, or one or two neutral beams for heating, at 400-800 kA plasma current, in conventional or “SuperX” divertor configurations. Equilibrium reconstructions provide key p…
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UKAEA-CCFE-CP(23)202021
Disruption prediction and avoidance is critical for ITER and reactor-scale tokamaks to maintain steady plasma operation and to avoid damage to device components. The present status and results from the disruption event characterization and forecasting (DECAF) research effort are shown. The DECAF paradigm is primarily physics-based and provides q…
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