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UKAEA-CCFE-PR(25)3512024
Fast ion (FI) loss properties in the presence of tearing mode and internal kink perturbations are numerically investigated for discharges in the MAST-U spherical tokamak, utilizing the MARS-F magnetohydrodynamic stability code and the REORBIT test particle guiding-center orbit-following module. Tracing about
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UKAEA-CCFE-PR(25)3502024
A key aspect in the modelling of magnetohydrodynamic (MHD) equilibria in tokamak devices is having access t…
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UKAEA-CCFE-PR(25)3492023
Tungsten is one of the primary materials of choice for several commercial fusion power plant designs, in particular for divertor targets and first wall. In maintenance conditions or during a loss of coolant accident, tungsten is expected to reach temperatures at which it readily volatilises as tungsten trioxide, potentially distributing radioactive…
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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-CCFE-PR(25)3772025
The vacancies and interstitials produced in high-energy collision cascades of irradiated tungsten can form prismatic dislocation loops with Burgers vectors 1⁄2⟨1 1 1⟩ and ⟨1 0 0⟩. The 1⁄2⟨1 1 1⟩ loops are very mobile, and their mobility is essential for the microstructure development of irradiated materials, It is a key parameter …
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UKAEA-STEP-CP(25)022022
Estimating costs of prototype or demonstration fusion power plants is difficult enough due to the often still preliminary designs combined with a non-existing supply chain for many bespoke technologies or materials. Extrapolating to commercial fusion power plants without a clear design is even harder and uncertainties are large. As a result, foreca…
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UKAEA-CCFE-CP(25)202019
As part of the preparation for the second JET DT campaign (DTE2), a series of isotope control experiments in H/D mixtures [1] have shown that NBI fuelling species has only a weak effect on the core isotope composition, which remains determined by the edge H/D ratio and therefore by the injected gas.
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UKAEA-CCFE-CP(25)192018
Unraveling the conditions that permit access to H-mode continues to be an unresolved physics issue for tokamaks, and accurate extrapolations are important for planning ITER operations and DEMO design constraints. Experiments have been performed in JET, with the ITER-like W/Be wall, to increase the confidence of predictions for the L-H transition po…
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UKAEA-CCFE-CP(25)182020
A study into the viability of a double null concept for DEMO has been undertaken as part of the work to address Key Design Integration Issues (KDIIs) within the DEMO powerplant. The objective of this study was to evaluate the feasibility of a double null architecture, featuring split blanket segments to enable a wider range of maintenance options…
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UKAEA-CCFE-PR(25)3472025
Background: The emergence and growth of fusion technology enables investigative studies into its applications beyond typical power production facilities. This study seeks to determine the viability of medical isotope production with the neutrons produced in an example large fusion device. Using FISPACT-II (a nuclear inventory code) and a simulated …
Showing 61 - 70 of 2477 UKAEA Paper Results