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UKAEA-CCFE-PR(26)4672025
Clean energy from nuclear fusion requires the development of an efficient technology for hydrogen isotope separation capable of high separation efficiency with lower energy costs and lower tritium inventory. Isotope separation using adsorbents such as zeolites and MOFs shows great promise due to their high isotope selectivity, but are limited to…
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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(24)2622023
STORM is a plasma turbulence code capable of simulating 3d turbulence across the full scrape-off layer of a tokamak fusion reactor, using a drift reduced, collisional fluid model. STORM uses mostly finite difference schemes, with a staggered grid in the direction parallel to the magnetic field. We describe the model, geometry and initialisation opt…
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UKAEA-CCFE-PR(24)2512023
The injection of energetic neutral particles into the plasma of magnetic confinement fusion reactors is a widely-accepted method for heating such plasmas; various types of neutral beam are also used for diagnostic purposes. Accurate atomic data are required to properly model beam penetration into the plasma and to interpret photoemission spectra…
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UKAEA-CCFE-PR(23)1892023
The separation of hydrogen isotopes is a vital step in preparing tritium and deuterium fuels for future fusion energy plants. This represents a fundamental challenge to fusion energy since the separation process must be able to handle high throughputs of hydrogen isotopes with a low tritium inventory, as tritium is highly radioactive and hazardo…
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UKAEA-CCFE-PR(23)1672023
A nonlinear 4-dimensional drift island theory derived in (Imada et al 2019 Nucl. Fusion 59 046016 and references therein) provides qualitative predictions of the plasma response to a stationary neoclassical tearing mode (NTM) magnetic island in a low beta, large aspect ratio tokamak plasma. (Dudkovskaia et al 2021 Plasma Phys. Control. Fusion 63 05…
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UKAEA-CCFE-PR(23)1182023
A new open source tool for fluid simulation of multi-component plasmas is presented, based on a flexible software design that is applicable to scientific simulations in a wide range of fields. This design enables the same code to be configured at run-time to solve systems of partial differential equations in 1D, 2D or 3D, either for transport (st…
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UKAEA-CCFE-PR(24)2412021
An intensive integrated modelling work of main scenarios of the new tokamak DTT (Divertor Tokamak Test facility) with the Single Null divertor configuration has been performed using first-principle quasi-linear transport models, in support to the design of the device and to the definition of its scientific work-programme. First results of this i…
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UKAEA-CCFE-PR(23)1032021
This paper provides an overview of the status of the laser diagnostics to be implemented on ITER. This includes descriptions of the Thomson scattering in the Core, Edge and Divertor regions, polarimetry and interferometry diagnostics used for measuring plasma density and also measurements of Helium density in the divertor using Laser Induced Flo…
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UKAEA-CCFE-PR(21)132020
Tridiagonal matrix inversion is an important operation with many applications. It arises frequently in solving discretized one-dimensional elliptic partial differential equations, and forms the basis for many algorithms for block tridiagonal matrix inversion for discretized PDEs in higher-dimensions. In such systems, this operation is often the …
Showing 1 - 10 of 32 UKAEA Paper Results