-
UKAEA-CCFE-PR(25)3942024
The MAST-U Super-X divertor provides the opportunity to study fusion plasma exhaust in novel conditions. However, in order to study these conditions advanced diagnostics are required. Following the development of the MAST-U Multi-Wavelength Imaging (MWI) diagnostic, we present the installation of a multi-delay coherence imaging spectroscopy (CIS…
-
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…
-
UKAEA-CCFE-PR(25)3562024
Abstract. A novel approach for efficient representation of three-dimensional (3D) tokamak equilibria is investigated, where a set of helical current filaments occupying the plasma region are employed to resolve deviations from the two-dimensional (2D) axi-symmetric state. A discrete set of 3D filaments, located at rational surfaces for a given t…
-
UKAEA-CCFE-PR(25)3502024
A key aspect in the modelling of magnetohydrodynamic (MHD) equilibria in tokamak devices is having access t…
-
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…
-
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…
-
UKAEA-CCFE-CP(25)132024
The end of tokamak operations at the Joint European Torus in December 2023 brought to a close the experimental life of an extraordinary fusion research facility.
-
UKAEA-CCFE-PR(25)3072024
We are introducing FAIR-MAST, a data management system designed for historical diagnostic data from the Mega Ampere Spherical Tokamak (MAST) fusion experiments. Following the FAIR (findability, accessibility, interoperability, and re-usability) principles, our system aims to address current accessibility issues with data that supports artificial in…
-
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…
-
UKAEA-CCFE-PR(25)2672024
The first generation of nuclear fusion reactors is expected to operate using a mixture of deuterium(D) and tritium(T) fuel. Controlling the D:T ratio is a promising option to control the fusion burn rate. The Joint European Torus (JET), as the only operational tokamak which can use tritium, is uniquely placed to test th…
Showing 21 - 30 of 530 UKAEA Paper Results