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UKAEA-STEP-PR(26)012025
We have investigated the response of detached plasmas to multi-ms timescale power transients using 1D simulations of the scrape-off layer on a scale and parameter range relevant for reactor-scale tokamaks, such as the Spherical Tokamak for Energy Production (STEP). Simulations were performed using the fluid code Hermes3, employing the solver CVODE…
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UKAEA-CCFE-PR(25)4032025
In its lifetime of around 40 years of scientific operations, JET has performed three full-scale DT experimental campaigns: one in 1997 (DTE1) and two more in a relatively quick succession in 2021 (DTE2) and 2023 (DTE3). One of the goals of these campaigns, apart from studying variety of physics effect relevant to DT plasmas, was demonstration of fu…
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UKAEA-CCFE-PR(25)3862025
In high performance regimes short (sub ms) bursts of heat and particles from the core (edge localised modes, ELMs) happen cyclically increasing temporarily the heat flux by 2-3 orders of magnitude, and this can hardly be tolerated by large tokamaks. If ELMs happen when the target is detached the plasma temporarily reattaches and looses energy in th…
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UKAEA-CCFE-PR(25)3392025
Fusion performance in a tokamak-reactor strongly depends on the confinement of thermalised α-particles (Helium (He) ash) in the core plasma region. Consequently, the development of He particle transport models and their validation in present experiments is an important step towards a more accurate prediction of fusion power production in future de…
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UKAEA-CCFE-PR(25)3362025
A method for determining the fast-ion population density in magnetically confined plasmas as a function of pitch-radius, (λ, R), using a solid-state neutral-particle analyzer (ssNPA) signal and neutral-beam injection (NBI) power-output data has been developed. Oscillations in the NBI power output are replicated only in the active part of the ssN…
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UKAEA-CCFE-PR(25)3092025
Neutral Beam Injection (NBI) is a powerful and very commonly used tool on machines used in the development of magnetically confined fusion power. Not all the neutral beam power is deposited within the plasma. This shinethrough power must be dealt with in the plasma vessel and any components irradiated by it must be protected against excessive he…
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UKAEA-CCFE-PR(25)3032025
Screening of high-Z (W) impurities from the confined plasma by the temperature gradient at the plasma periphery of fusion-grade H-mode plasmas was demonstrated for the first time in JET with the Be/W wall [Field A R et al, Nucl. Fusion 63(2023) 016028]. Through careful optimisation of the hybrid-scenario, deuterium plasmas with sufficient heating p…
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2025
This work examines the separatrix and SOL characteristics in three scenarios on JET: the Quasi-Continuous Exhaust (QCE) regime, the core-edge-SOL integrated ITER Baseline scenario, and the X-point Radiator (XPR) regime. All three scenarios are potentially compatible with reactor operations, as they aim to provide power exhaust solutions through dif…
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UKAEA-STEP-PR(25)292025
Systems models and associated cost analyses are widely used within the fusion community to analyse tokamak designs, from prototype and demonstrator machines to potential commercial fusion power plants. To ensure the design programmes of fusion prototype/demonstrator power plants deliver a cost optimised design (within existing uncertainty limita…
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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 rel…
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