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UKAEA-STEP-PR(24)182024
This paper presents a comprehensive overview of the preliminary divertor design and plasma exhaust scenario for the reactor-class Spherical Tokamak for Energy Production (STEP) project. Due to the smaller size of the machine, with a major radius less than half that of most DEMO concepts, the current design features a double-null divertor geometr…
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UKAEA-STEP-PR(24)192023
SOLPS-ITER simulations performed on STEP CDN geometry with Ar, varying D2 fuelling location Fuelling location can be an actuator for impurity compression/enrichment Inner-midplane (IMP) fuelling enhanced Ar compression/enrichment by 1) driving main plasma outflow 2) increasing collision frequency and 3) lowering upstream temperature PFR+IMP fuel…
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UKAEA-STEP-PR(24)162023
The STEP (Spherical Tokamak for Energy Production) fusion programme aims to produce net energy as a prototype fusion energy plant in the 2040s. To find an exhaust solution which is compatible with the core, we need to achieve high impurity enrichment. In this study, we investigated the impact of deuterium gas puff location on impurity enrichme…
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UKAEA-CCFE-CP(24)032023
Measurements are presented, alongside corresponding interpretative SOLPS-ITER simulations, of the first MAST-U experiments comparing ohmically heated L-mode fuelling scans in Conventional divertor (CD) and Super-X divertor (SXD) configurations. In experiment, at comparable outer mid-plane separatrix electron density, ne,sep,OMP, the maximum lower o…
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UKAEA-STEP-CP(23)122023
In order to achieve a compatible solution between the divertors and the core, SOLPS-ITER simulations were performed on STEP (Spherical Tokamak for Energy Production) connected double-null geometry to investigate the possibility of using deuterium (D) fuelling puff locations as an actuator for divertor argon (Ar) retention. Significant reduction of …
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UKAEA-STEP-PR(23)142023
The tungsten erosion within STEP assuming tungsten main wall and tungsten divertor has been estimated with ERO at the inner and outer divertor, at the inner and outer midplane and at the outboard baffle entrance. Plasma parameters are based on SOLPS simulations applying argon puffing for edge cooling. The modelled peak gross erosion is highest with…
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UKAEA-CCFE-PR(23)1452023
In this manuscript we present the recently developed flexible framework for building both fluid and electron kinetic models of the tokamak Scrape-Off Layer in 1D - ReMKiT1D (Reactive Multi-fluid and Kinetic Transport in 1D). The framework can handle systems of non-linear ODEs, various 1D PDEs arising in fluid modelling, as well as PDEs arising from…
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UKAEA-CCFE-PR(23)1322023
First quantitative analysis of the detachment processes in the MAST Upgrade Super-X divertor show an unprecedented impact of plasma-molecular interactions involving molecular ions (likely $D_2^+$), resulting in strong ion sinks, leading to a reduction of ion target flux. This starts to occur as the ionisation source detaches from the target, lea…
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UKAEA-CCFE-PR(23)1282022
Predictions of the impact of charge-exchange (CX) reactions on beam ions in the MAST Upgrade spherical tokamak have been compared to measurements carried out with a fission chamber (neutron fluxes) and a Fast Ion Deuterium-Alpha (FIDA) diagnostic. A simple model was developed to reconstruct the outer-midplane neutral density based on Thomson sca…
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UKAEA-STEP-PR(23)072022
To mitigate the issue of plasma exhaust in reactor scale tight aspect ratio tokamaks such as STEP (Spherical Tokamak for Energy Production), a double-null (DN) configuration is thought to be advantageous over a single-null (SN) configuration. However, practical control of the plasma vertical stability will likely lead to an oscillation around th…
Showing 1 - 10 of 45 UKAEA Paper Results