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UKAEA-CCFE-PR(25)3752025
The National Spherical Torus Experiment (NSTX) at the Princeton Plasma Physics Laboratory in the United States, and the Mega Ampere Spherical Tokamak (MAST) at the United Kingdom Atomic Energy Authority in the United Kingdom, and their respective upgrades (NSTX-U and MAST-U) are two mega-amp class spherical tokamak fusion devices that have operated…
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UKAEA-CCFE-PR(25)3622025
In this work we present the assessment framework for magnetic equilibrium controllers on MAST-U spherical tokamak. Such controllers are essential for MAST-U since exhaust physics and core-edge integration studies require advanced divertor plasma configurations. The developed framework is based on the TokSys suite of plasma control codes, which was …
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UKAEA-CCFE-PR(25)3052025
The MAST Upgrade Super-X divertor is typically seen to detach in steady state discharges. However, divertor re-attachment is observed to occur during fast transient heat loads. In this paper the effect of edge localised modes (ELMs) on the divertor are diagnosed on fast time scales with Thomson scattering and with a new ultrafast divertor spectrosc…
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UKAEA-CCFE-PR(25)3692024
Plasma detachment in tokamaks is useful for reducing heat flux to the target. It involves interactions of the plasma with impurities and neutral particles, leading to significant losses of plasma power, momentum, and particles. Accurate mapping of plasma emissivity in the divertor and X-point region is essential for assessing the relationship bet…
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UKAEA-CCFE-PR(25)3512024
Fast ion (FI) loss properties in the presence of tearing mode and internal kink perturbations are numerically investigated for discharges in the MAST-U spherical tokamak, utilizing the MARS-F magnetohydrodynamic stability code and the REORBIT test particle guiding-center orbit-following module. Tracing about
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UKAEA-CCFE-PR(25)3112024
2D electron density profiles obtained from coherence imaging spectroscopy in different MAST-U divertor conditions are compared. The data includes variations of strike point position, core electron density, and heating power. The improved performance of the long-legged divertors results in a lower electron density and particle flux at the target …
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UKAEA-STEP-PR(24)182024
This paper presents a comprehensive overview of the preliminary divertor design and plasma exhaust scenario for the reactor-class Spherical Tokamak for Energy Production (STEP) project. Due to the smaller size of the machine, with a major radius less than half that of most DEMO concepts, the current design features a double-null divertor geometr…
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UKAEA-CCFE-PR(24)2142024
In order to test the capability of the full electromagnetic DYON to predict the plasma initiation feasibility of individual discharges and thus the operating space in the device, a dedicated experimental database was built in MAST-U by scanning the prefilled gas pressure $p_0$ and the induced loop voltage $V_{loop}$ (3 failed breakdown discharge…
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UKAEA-CCFE-CP(25)152023
Reduced plasma models play a pivotal role in swiftly interpreting experiments, exploring different reactor design points, and providing consistency checks for high-fidelity simulations. This presentation focuses on reduced models for plasma detachment onset and transient reattachment timescales, assessing their validity across ASDEX Upgrade, JET…
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UKAEA-CCFE-CP(24)142023
Accurate quantification of the power loss channels and overall power balance of the plasma is essential for the safe operation of current and future fusion devices. The relative magnitudes of core radiation, SOL radiation and divertor target heat loading are determining factors in both PFC design and plasma scenario design in the successful real…
Showing 1 - 10 of 94 UKAEA Paper Results