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UKAEA-CCFE-PR(23)992023
The DT fuel cycle is rather different to other nuclear fusion topics: it involves handling of a very precious and radiotoxic gas, i.e. tritium, together with deuterium, processing of gaseous, liquid and solid hydrogen isotopologues, treatment of deuterated and tritiated species, and removal and recovery of deuterium / tritium from water and othe…
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UKAEA-CCFE-CP(23)062020
The paper looks at a selective smelting regime where higher activity components are smelted with lower activity components with the aim to reduce the amount of ILW waste for disposal. This has been applied to the European DEMO Fusion Plant HCPB 2015 baseline design waste assessment. The paper assesses the structural steels in the breeder blanket…
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UKAEA-CCFE-CP(22)112022
The tritium inventory of future fusion power plants needs to be monitored in the fuel cycle for several reasons; to comply with limits imposed by environment and safety regulators, adhere to practises required by nuclear regulators and for process control purposes. Fulfilling all these requirements leads to a comprehensive list of locations in the …
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UKAEA-CCFE-PR(22)462022
An initial safety analysis of a preliminary DEMO tritium fuel cycle has been undertaken using functional failure mode and effects analysis (FFMEA) to create accident scenarios for evaluation. A total of ten scenarios were developed and analysed based upon the current technology planned for the tritium fuel cycle. The findings indicate that the pote…
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UKAEA-CCFE-PR(22)302022
In the Pre-Concept Design Phase of EU DEMO, the work package TFV (Tritium – Matter Injection – Vacuum) has developed a smart and tritium self-sufficient three-loop fuel cycle architecture. Driven by the need to reduce the tritium inventory in the systems to an absolute minimum, this requires the continual recirculation of gases in loops without…
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UKAEA-CCFE-PR(22)072022
Self-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simulating microstructures generated by neutron irradiation in tungsten components of a fusion reactor. Electron microscopy has been used to characterize defects formed in tungsten samples by ion irradiation and estimate their density and size distribution. Some of the sample…
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UKAEA-CCFE-CP(20)1162020
The ITER Tokamak Exhaust Processing (TEP) system relies on palladium membrane reactors (PMRs) for tritium recovery. The PMR consists of a palladium/silver membrane permeator filled with a catalyst, that can be used to recover hydrogen species (most importantly tritium) from methane and water impurities present in fusion reactor exhaust emissions…
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UKAEA-CCFE-PR(18)782018
The public acceptability of emerging industrial technologies, can affect their chances of commercial success. In large, demographically diverse samples from the United Kingdom (N = 438) and Germany (N = 390) – recruited to an online questionnaire-based survey study – we show for the first time the stigmatizing impact that t…
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UKAEA-CCFE-PR(19)142019
How the Archean felsic crust grew from its mafic precursors between 3.8 and 2.5 billion years ago remains elusive and the subject of great debate. Here, we present silicon isotopic constraints on Tonalite-Trondhjemite-Granodiorite (TTG) and Granite-Monzonite-Syenite (GMS) plutons from the Kaapvaal craton, which range in age from 3.55 to 2.69 Ga.…
Showing 11 - 19 of 19 UKAEA Paper Results