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UKAEA-STEP-PR(26)122025
The Spherical Tokamak for Energy Production (STEP) is the UK’s flagship program to design a prototype fusion power plant capable of delivering net electricity to the grid. Due to geometric constraints in spherical tokamaks, STEP is being developed for fully non-inductive operation, relying primarily on microwav…
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UKAEA-CCFE-PR(25)3152025
Neutral Beam Injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed Deuterium-Tritium Experimental campaign (DTE2) on the JET device. High NBI power was required for high fusion yield and alpha particle studies and to …
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UKAEA-STEP-PR(26)052024
STEP is a spherical tokamak prototype power plant that is being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models to optimise fusion performance subject to satisfying various physics and engineering constraints. A modelling workflow, including integrated core plasma modelling, MHD stability a…
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UKAEA-STEP-PR(24)222024
The architecture of STEP has been developed to enable a hybrid maintenance approach, using ports in the vacuum vesselor a limited list of tasks that must be performed shortly after shutdown, and larger openings to simplify and speed-up major refits. Robotic handling systems in zero-human entry facilities will prevent workers from being exposed t…
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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(26)4412023
The pre-thermal quench (pre-TQ) dynamics of a pure deuterium (D2) shattered pellet injection (SPI) into a 3 MA/7MJ JET H-mode plasma is studied via 3D non-linear MHD modelling with the JOREK code. The interpretative modelling captures the overall evolution of the measured density and radiated power. The simulations also identify the importance of t…
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UKAEA-CCFE-PR(24)2482023
This work describes the usage of Error Field Correction coil system [Barlow I. et al 2001 Fusion Eng. Des. 58-59 189], which is a set of 4 coils located external to the vessel of the JET device, with the aim of introducing non-axisymmetric n=1 magnetic field perturbations in various targeted plasma experiments. Besides being used to characterize…
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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-CCFE-PR(23)1832023
The development of improved designs for components which will be subject to high heat fluxes has been identified as a critical challenge for the realisation of commercial fusion power. This paper presents details of a facility which allows early verification of thermofluid and thermomechananical performance of prototype components and enables compa…
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UKAEA-CCFE-PR(23)1802023
Showing 1 - 10 of 74 UKAEA Paper Results