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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…
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UKAEA-CCFE-PR(24)2562024
An absolutely calibrated, visible imaging diagnostic has been deployed on the MAST spherical tokamak. Two sets of three colour channels are defined using a combination of stacked multi-cavity interference filters, colour-glass filter and a colour-pixel sensor. The system is compact with a single viewing pupil which facilitates unambiguous compariso…
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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-CCFE-PR(24)2142024
In order to test the capability of the full electromagnetic DYON to predict the plasma initiation feasibility of individual discharges and thus the operating space in the device, a dedicated experimental database was built in MAST-U by scanning the prefilled gas pressure $p_0$ and the induced loop voltage $V_{loop}$ (3 failed breakdown discharge…
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UKAEA-CCFE-CP(24)142023
Accurate quantification of the power loss channels and overall power balance of the plasma is essential for the safe operation of current and future fusion devices. The relative magnitudes of core radiation, SOL radiation and divertor target heat loading are determining factors in both PFC design and plasma scenario design in the successful real…
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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-CP(24)042023
In 2019 the UK launched the STEP programme to design and build a prototype electricity producing nuclear fusion power plant, aiming to start operation around 2040. The plant should lay the foundation for the development of commercial nuclear fusion power plants. The design is based on the spherical tokamak principle, which opens a route to high pre…
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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-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…
Showing 1 - 10 of 33 UKAEA Paper Results