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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)772021
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Power Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed in order to identify key open R&D issues. The as…
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UKAEA-CCFE-PR(21)792021
Reconstructions of plasma equilibria using magnetic sensors and a Dα constraint were routine during operation of the MAST spherical tokamak, but reconstructions using kinetic profiles was not. These are necessary for stability and disruption analysis of the MAST database, as well as going forward for operation in the upgrade to the device, MAST…
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UKAEA-CCFE-PR(21)782021
Alfvén eigenmode (AE) instabilities driven by alpha-particles have been observed in D-3He fusion experiments on the Joint European Torus (JET) with the ITER-like wall (ILW). For the efficient generation of fusion alpha-particles from D-3He fusion reaction, the 3‑ion radio frequency (RF) scenario was used t…
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UKAEA-CCFE-PR(21)772021
The optimum conditions for access and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed. The assessment is performed on the basis of empirical and…
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UKAEA-CCFE-PR(21)762021
We present the first parallel electron transport results obtained using the newly developed 1D transport code SOL-KiT. In order to properly predict divertor heat loads it is of key importance to develop a thorough understanding of discrepancies between different parallel transport modelling approaches. With the capability to self-consistently sw…
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UKAEA-CCFE-PR(21)752021
Eurofer97 steel is a primary structural material for the plasma facing-components of future fusion reactors. Laser welding is a promising technique that can overcome the challenges of remote handling and maintenance. However, the interaction of the induced residual stress distribution with the heterogeneous microstructure may degrade the mechanical…
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UKAEA-CCFE-PR(21)742021
An important contribution to the mechanical stresses present in the ITER ICH antenna is related to the non-uniform heating of its front section due to RF losses, plasma and charge exchange, and the effects of neutron radiation. As a consequence, intensive convective cooling is necessary to maintain temperature and the related thermally induced s…
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UKAEA-CCFE-PR(21)732021
During bursty MHD events, transient ion cyclotron emission (ICE) is observed from deuterium plasmas in the Large Helical Device (LHD) heliotron-stellarator. Unusually, the frequencies of the successive ICE spectral peaks are not close to integer multiples of the local cyclotron frequency of an energetic ion population in the likely emitting regi…
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UKAEA-CCFE-PR(21)722021
During the design process of fusion reactors it is desirable to rapidly prototype different design concepts and assess their suitability against a range of high level requirements. This helps to narrow the design window and scope out potential designs which can undergo further more detailed analysis. The Paramak is an open-source tool that aims …
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