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UKAEA-STEP-PR(24)212024
The design, delivery, and operation of a large-scale infrastructure project is challenging at best. For the Spherical Tokamak for Energy Production (STEP) Prototype Powerplant (SPP), the challenges increase exponentially. In addition to being a large-scale infrastructure project, it is a cutting edge, first of a kind (FOAK) technology demonstrat…
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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)122024
Ensuring tritium fuel self-sufficiency while maintaining continuous and high specification fuel flow to the tokamak via a low tritium inventory and controllable fuel cycle is a significant challenge to the STEP plant design. Effective and high-quality fuelling and exhausting is required to sustain and control a stable plasma, whereas fuel suffic…
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UKAEA-CCFE-PR(24)2232024
With more public and private funding in fusion, the expectations in terms of spillover benefits are increasing, but these can only happen through enhanced cross-sector collaboration. Across the world, fusion research has historically been funded through public programmes, resulting in a huge breadth and depth of expertise and intellectual propert…
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UKAEA-STEP-PR(24)092024
The STEP Prototype Powerplant (SPP) will be a first of a kind powerplant – its prime objective is to export electrical power, to the grid, above 100MWe. As part of a wider issue, addressing the STEP concept design, this paper seeks to explore how electrical power will be generated from a Spherical Tokamak heat source. Accordingly, the followin…
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UKAEA-STEP-PR(24)082024
Tritiated water will be present in many demonstrator class fusion devices in a wide array of locations and concentrations. Accurate and fast measurement will be a key requirement to ensure suitable process monitoring, safety assurance and tritium tracking is in place. This work quantifies the deuterium detection limits achievable using a bench…
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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-PR(26)4462023
This work investigated the impact of electron beam (EB) welding, and in particular varying the transverse speed of the electron beam (i.e. 1200-2200 mm/min), on the resultant microstructure of PM2000 ODS steel, using analytical electron microscopy and microhardness. The resultant range of heat inputs during welding explored in this study (72-39 J/m…
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UKAEA-CCFE-PR(26)4452023
MARS-F (Liu et al 2000 Phys. Plasmas 7 3681 ) simulations of plasma response in MAST-U highlight the possibility to measure directly the changes in plasma response as a function of the applied 3D field poloidal spectrum, in order to identify the best coil configuration to achieve Edge Localized Mode (ELM) suppression. Achieving ELM suppression in s…
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UKAEA-CCFE-CP(26)412023
In 2021 JET exploited its unique capabilities to operate with T and D–T fuel with an ITER-like Be/W wall (JET-ILW). This second major JET D–T campaign (DTE2), after DTE1 in 1997, represented the culmination of a series of JET enhancements—new fusion diagnostics, new T injection capabilities, refurbishment of the T plant, increased auxiliary h…
Showing 41 - 50 of 353 UKAEA Paper Results