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UKAEA-CCFE-CP(19)062019
The next D-T campaign will push JET ITER-like Wall (IWL) to high divertor power and energy levels. During the 2016 campaign, the Strike Point (SP) sweeping permitted relevant H-mode scenarios without exceeding the temperature limits imposed by JET Operation Instructions (JOIs). In the subsequent shutdown, six outer divertor tungsten-coated 2D carbo…
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UKAEA-CCFE-CP(19)052019
This paper presents the methodology and results of developing and implementing a system-of-systems architecture for controlling many robotic systems within the context of industrial facilities, where the life of the facility will be far longer than the life of the robotics, due to software updates and accelerated digital obsolescence. The use cases…
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UKAEA-CCFE-CP(19)042018
Waste-production predictions for the future demonstration fusion power plant (DEMO) are necessary to produce an accurate picture of the likely environmental and economic costs of radioactive waste disposal at end-of-life (EOL). Even during the conceptual stage of DEMO design it is important to perform waste assessment so as to avoid potential surpr…
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UKAEA-CCFE-CP(19)032019
The European Spallation Source (ESS) is a multi-disciplinary research facility which will be the world’s most powerful pulsed neutron source. A critical component of ESS will be a facility for handling radioactive waste and preparing it for safe disposal. Safe disposal of ESS waste requires the dexterous tele-manipulation of large, highly activat…
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UKAEA-CCFE-CP(19)022019
Nuclear decommissioning environments are challenging and hazardous, typically involving high temperatures, pressures and extreme radiation. Robotic devices are commonly used to complete tasks within challenging environments, which would otherwise pose a risk to human health, however remotely operating robots without full three-dimensional vision is…
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UKAEA-CCFE-CP(19)012019
The maintenance, replacement and decommissioning of future nuclear fusion reactors will require quick and reliable cutting and joining of in-vessel pipework. Initial design studies for nuclear fusion reactors for power generation have estimated cutting and welding could account for up to 60% of the maintenance duration using conventional in-situ pr…
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UKAEA-CCFE-PR(19)702019
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UKAEA-CCFE-PR(19)692019
The equipment used in some welding techniques (e.g. tungsten inert gas alternating current welding or capacitor discharge stud welding) can induce high electromagnetic fields inside the operator due to the large time-varying electric currents involved in the process. The European Union (EU) Directive 2013/35/EU provides guidelines and recommendatio…
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UKAEA-CCFE-PR(19)682019
We report a theoretical study of microstructure, magnetic properties, and their relationship in relatively concentrated Fe-Cr alloys in both Fe- and Cr-rich regions. Annealing of initially random systems at 500° C for times of the order of 106 s substantially changes their microstructure. In both systems, solute atoms form clusters with…
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UKAEA-CCFE-PR(19)672019
Analysis of the L-H and H-L transition power thresholds (Pth) and pedestal parameters are presented for the Mega Ampere Spherical Tokamak (MAST). The dependencies of Pth on the average, core plasma electron density, X-point height and plasma current are described. Increasing X-point distance from the divertor floor over 10-12 cm, is found to inc…
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