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UKAEA-CCFE-PR(26)4602024
In Joint European Torus with beryllium as a main impurity in the plasma, the confined fusion α-particle diagnosing was based on detection of γ-rays due to the 9Be(α,nγ)12C nuclear reaction. The same diagnostic approach was accepted in the earlier International Thermonuclear Experimental Reactor designed with B…
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UKAEA-CCFE-PR(26)4572024
The Yacora solver has been used to generate two novel molecular rate databases for use in SOLPS-ITER. The reduced Yacora database utilises updated cross-sectional data, whilst the full Yacora database includes the same updated cross-sectional data in addition to the inclusion of vibrational reactions such as off-diagonal vibrational electron-impact…
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UKAEA-CCFE-PR(26)4562024
A Gas Electron Multiplier (GEM) based detector was exploited for the first time on the MASTU tokamak during the 2023 campaign to investigate Soft X-Ray (SXR) radiation (1-20keV) emitted from the plasma. SXR radiation carries essential information on electron temperature and density, impurity presence, and Magneto-hydrodynamic (MHD) activities, m…
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UKAEA-CCFE-PR(26)4552024
The linear MHD peeling-ballooning stability analysis on the ELM-free phase of MAST Upgrade H-mode plasma is presented. In contrast to other similar discharges, #47018 is found to have significantly higher and wider pedestal during an ELM-free H-mode phase that lasts for approximately 80ms, which is made possible by the reduced core MHD mode acti…
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UKAEA-CCFE-PR(26)4532024
Experimental campaigns at the Joint European Torus with an ITER-like Be/W wall (JET-ILW) with pure deuterium (D), tritium (T) and Deuterium-Tritium (DT) were a unique opportunity to explore various aspects related to the ITER operation. It should also be emphasized that the JET campaign at the end of 2021 included the first tokamak experiments u…
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UKAEA-CCFE-PR(26)4512024
An understanding of the behaviour of the D or He fuel used in tokamak discharges is essential in analyses such as modelling edge and divertor transport and the erosion of the vessel walls. However, poor agreement is found between measurements made on the JET tokamak and collisional-radiative models used …
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UKAEA-CCFE-PR(26)4502024
In magnetic fusion devices, undesired non-axisymmetric magnetic field perturbations, typically called error fields (EF), have been observed to have a detrimental effect on plasma stability and confinement and can lead to a brute plasma termination, i.e. plasma disruption events (Buttery et al 1999, Nuc. Fus. 39, 1827). The main strategies that c…
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UKAEA-CCFE-CP(26)452024
A real-time plasma magnetic equilibrium controller has been developed to aid in the precise control of advanced configurations such as double-null, super-X, X-point target and X-divertor for the first time on the MAST Upgrade (MAST-U) tokamak. Successful real-time magnetic equilibrium control of different plasma shape control variables during th…
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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)4452023
MARS-F (Liu et al 2000 Phys. Plasmas 7 3681 ) simulations of plasma response in MAST-U highlight the possibility to measure directly the changes in plasma response as a function of the applied 3D field poloidal spectrum, in order to identify the best coil configuration to achieve Edge Localized Mode (ELM) suppression. Achieving ELM suppression in s…
Showing 1 - 10 of 451 UKAEA Paper Results