Sarah Bickerton Rob Felton Sarah Medley Dr Rebecca C. R. Shaw Hannah Todd Fatimah Sanni Dr Damien King Sandra Romanelli the JET Contributors
Following the first Deuterium-Tritium Experiment (DTE1) at UKAEA, modifications were investigated to the Joint European Torus’ (JET) gas introduction systems to increase the gas feed capabilities of the JET facility to better support future campaigns. The gas introduction systems comprise the gas introduction and gas distribution system (GI/GD)…
PreprintF. Schoofs T. N. Todd
We describe a workflow that is able to approximate basic machine parameters (including but not limited to plasma current IP, major radius R0, toroidal magnetic field B0, fusion power Pfusion) based on the choice of maximum field BTF,max on the in-boa…
Preprint PurchaseAlexander J. Leide Matthew J. Lloyd Richard I. Todd David E. J. Armstrong
Raman spectroscopy has been used to identify defective bonding in neon and silicon ion irradiated single crystals of 6H-SiC. Observable differences exist in the CC bonding region corresponding to different defect structures for neon and silicon ion implantations. Evidence of oxidation during high temperature ion implantation is observed as C-O a…
PreprintAlexander J. Leide Edmund Tarleton Richard I. Todd David E. J. Armstrong
Ion implantation is widely used as a surrogate for neutron irradiation in the investigation of radiation damage on the properties of materials. Due to the small depth of damage, micromechanical methods must be used to extract material properties. In this work, nanoindentation has been applied to ion irradiated silicon carbide to extract radiatio…
PreprintAlexander J. Leide Richard. Todd David E. J. Armstrong
Focussed ion beam (FIB) milling can be used to reveal sub-surface fracture and deformation below indents in materials. However, evolution of residual stresses around the indent impression cause changes to the crack morphology during the FIB cross-sectioning procedure. Berkovich nanoindents in single crystal hexagonal (6H) silicon carbide cause r…
PreprintD. Hancock D. Homfray M. Porton I. Todd B. Wynne
Tungsten has long been the favoured armour material for plasma facing high heat flux components proposed for future fusion reactors, but studies examining the use of tungsten or other refractory metals in the underlying cooled structures have historically excluded them, leaving current concepts heavily dependent on copper alloys such as copper chro…
Preprint PublishedD. Hancock D. Homfray M. Porton I. Todd B. Wynne R. Bamber K. Flinders P. Jepson H. Lewtas H. Robinson
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…
PreprintZ. Leong J.S. Wróbel S.L. Dudarev R. Goodall I. Todd D. Nguyen-Manh
Multicomponent systems, termed High Entropy Alloys (HEAs), with predominantly single solid solution phases are a current area of focus in alloy development. Although different empirical rules have been introduced to understand phase formation and determine what the dominant phases may be in these systems, experimental investigation has revealed tha…
Preprint PublishedS. Zheng D. B. King L. Garzotti E. Surrey T. N. Todd
It has long been recognised that the shortage of external tritium sources for fusion reactors using D-T, the most promising fusion fuel, requires all such fusion power plants (FPP) to breed their own tritium. It is also recognised that the initial start-up of a fusion reactor will require several kilograms of tritium within a scenario in which radi…
Preprint PublishedS. Zhen T.N. Todd
The existing tritium resource available for future fusion power plant D-T operation is severely limited. It is essential to breed tritium to maintain the continuous consumption in the D-T plasma so as to sustain the required fusion power. A minimum criterion of calculated tritium breeding ratio (TBR) >1.1 is adopted to ensure tritium self-sufficien…
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