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UKAEA-CCFE-CP(25)292023
INTRODUCTION Future generation tokamaks, including ITER, will strive for better confinement, which means a higher fusion plasma current to achieve a good Fusion Efficiency Factor value greater than 10 [1]. One of the major threats with this scenario is a potential for increased damage of first wall components due to unmitig…
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UKAEA-CCFE-PR(24)2502023
In the quest of new materials that can withstand severe irradiation and mechanical extremes for advanced applications (e.g. fission & fusion reactors, space applications, etc.), design, prediction and control of advanced materials beyond current material designs become paramount. Here, through a combined experimental and simulation methodol…
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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-CCFE-PR(23)1522023
This article presents an in-depth study of the sequence of events leading to density limit disruption in J-TEXT tokamak plasmas, with an emphasis on boudary turbulent transport and the high-field-side high-density (HFSHD) front. These phenomena were extensively investigated by using Langmuir probe and Polarimeter-interferometer diagnostics. The res…
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UKAEA-CCFE-PR(22)492022
In the quest of new materials that can withstand severe irradiation and mechanical extremes for advanced applications (e.g. fission reactors, fusion devices, space applications, etc), design, prediction and control of advanced materials beyond current material designs become a paramount goal. Here, though a combined experimental and simula…
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UKAEA-CCFE-PR(23)1032021
This paper provides an overview of the status of the laser diagnostics to be implemented on ITER. This includes descriptions of the Thomson scattering in the Core, Edge and Divertor regions, polarimetry and interferometry diagnostics used for measuring plasma density and also measurements of Helium density in the divertor using Laser Induced Flo…
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UKAEA-CCFE-PR(21)802021
This article reports the first observation of the high-field side high density (HFSHD) in the limiter devices. In the J-TEXT high density discharges, the high-density front at the HFS scrape-off layer (SOL) region edge has been clearly identified by the far-infrared laser polarimeter-interferometer. The HFSHD forms at the HFS SOL, and then expan…
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UKAEA-CCFE-PR(21)022021
In quiescent H-mode (QH-mode) regime, edge harmonic oscillations (EHOs) are believed to provide necessary radial transport to prevent occurrence of large edge localized modes. A systematic modeling study is performed here on the low-n EHOs in a DIII-D QH-mode plasma [Chen et al. 2016 Nucl. Fusion 56 076011], by utilizing the MARS-Q code [Liu et a…
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UKAEA-CCFE-PR(21)202020
In the worlds of nuclear energy, mining, petrochemical processing, and sub-sea, robots are being used for an increasing number and range of tasks. This is resulting in ever more complex robotics installations being deployed, maintained, and extended over long periods of time. Additionally, the unstructured, experimental, or unknown operational cond…
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UKAEA-CCFE-CP(20)792018
The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…
Showing 11 - 20 of 25 UKAEA Paper Results