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UKAEA-CCFE-PR(26)4322026
Pyvale is an open-source software package that aims to become an all-in-one tool for sensor simulation, sensor uncertainty quantification, sensor placement optimization, and calibration/validation. Central to this is support for image-based sensors, with a dedicated Digital Image Correlation (DIC) module designed for both standalone use and integra…
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UKAEA-STEP-PR(26)122025
The Spherical Tokamak for Energy Production (STEP) is the UK’s flagship program to design a prototype fusion power plant capable of delivering net electricity to the grid. Due to geometric constraints in spherical tokamaks, STEP is being developed for fully non-inductive operation, relying primarily on microwav…
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UKAEA-STEP-PR(26)022025
Alternative Divertor Configurations (ADCs) often make use of high total flux expansion (fR) and connection length (L∥) to improve the access to and the controllability of detachment, a regime vitally important for reactor-class tokamaks such as the Spherical Tokamak for Energy Production (STEP). However, there has been little effort in assessi…
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UKAEA-CCFE-PR(26)4612024
Self-passivating W-11.4Cr-0.6Y (in wt.%) alloy is the plasma-facing armour material candidate in fusion power plants. In the present work, the as-sintered material, fabricated via ball milling and field-assisted sintering, was annealed at 1000℃ for varying durations to induce phase decomposition. This process leads to the transformation of the in…
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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-STEP-PR(26)052024
STEP is a spherical tokamak prototype power plant that is being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models to optimise fusion performance subject to satisfying various physics and engineering constraints. A modelling workflow, including integrated core plasma modelling, MHD stability a…
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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-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(24)2672024
The self-passivating yttrium-containing WCr alloy has been developed and researched as a potential plasma-facing armour material for fusion power plants. This study explores the use of yttria (Y2O3) powders instead of yttrium elemental powders in the mechanical alloying process to assess their applicability in this material. Fabricated through f…
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UKAEA-STEP-PR(24)202024
Success of UKs STEP (Spherical Tokamak for Energy Production) programme [1] [2] [3] [4] requires a robust plasma control system. This system has to guide the plasma from initiation to the burning phase, maintain it there, producing the desired fusion power for the desired duration and then terminate the plasma safely. This has to be done in a ch…
Showing 1 - 10 of 188 UKAEA Paper Results