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UKAEA-STEP-CP(26)012024
The Spherical Tokamak for Energy Production (STEP) programme aims to deliver a UK prototype fusion energy plant, targeting 2040, and a path to commercial viability of fusion. The conceptual design of such a prototype, meeting engineering and physics constraints, is complex due to the tight aspect ratio and limited space in compact spheri…
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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…
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UKAEA-STEP-PR(25)312024
A strategy to prevent concentrated deposition of the exhaust power in a fusion device is to seed a localised ‘divertor’ region with impurity gas, which is chosen to radiate predominantly at the cooler electron temperatures associated with the plasma edge. If this impurity travels upstream to the main confined plasma, it can significantly impact…
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UKAEA-CCFE-PR(25)3202024
The development of a high current baseline scenario (I_p = 3.5MA, q95 ~3.0, beta_N < 2) in deuterium (D), tritium (T) and deuterium-tritium (D-T) for high DT fusion performance at JET with Be/W wall is described. We show that a suitable scenario capable of delivering up to 10 MW of fusion power, depending on the auxiliary heating power avail…
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UKAEA-CCFE-CP(25)092024
The successful development of fusion power will rely on the key technology of breeder blanket components. These components surround the fusion plasma, providing significant heat for power generation, and breeding the tritium fuel on which the plasma reaction depends. However, the technology for these components remains at a low technology readin…
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UKAEA-CCFE-PR(25)2972024
During detachment, a buffer of neutral atoms and molecules builds up between the target and the ionising plasma. Collisions between the plasma and the molecules play an important role in the detachment process. Studies of plasma-molecular kinetics indicate that the gas temperature is increased during detachment for a wide range of conditions on …
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