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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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UKAEA-CCFE-PR(25)3632024
The extreme working conditions of the in-vessel components in nuclear fusion reactors require remote laser-welding for maintenance. However, this process induces heterogeneous residual stress, which can interact with microstructures, degrading mechanical properties. Involving the high-temperature operating environmen…
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UKAEA-CCFE-PR(25)3602024
Determination of the absolute neutron rate production in any fusion device and in particular for ITER and future power plants is essential for their operation and for the optimization of the fusion power. A common calibration approach is to use a well characterized neutron sources placed inside the vacuum vessel combined with Monte Carlo simula…
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UKAEA-CCFE-PR(25)3572024
Profiles of power deposition on the first wall of the Joint European Torus (JET) tokamak experiment are fitted by tracing an analytic representation for the distribution of power from midplane along lines of magnetic field. The technique is used to help design plasma facing components (PFCs) in reactor-scale magnetic confinement devices, hence un…
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UKAEA-CCFE-PR(25)3482024
Determining stress and strain in a component of a fusion power plant involves defining boundary conditions for the mechanical equilibrium equations, implying the availability of a full reactor model for defining those conditions. To address this fundamental challenge of reactor design, a finite element method (FEM) model for the Mega-Ampere Spheric…
Showing 11 - 20 of 500 UKAEA Paper Results