M. J. Lloyd C. Teoh G. Lim D. Nguyen-Manh D. Sobieraj J. S. Wrobel R. E. Simpson
The realisation of fusion energy depends on the development of advanced materials for challenging environments. Rapid screening of prototype alloys using magnetron sputtering and high throughput characterisation is currently being applied to candidate W alloys with improved mechanical performance, reduced activation and tolerance to damage from neu…
PreprintD. Nguyen-Manh J.S. Wrobel M. Klimenkov M.J. Lloyd L. Messina S.L. Dudarev
Understanding how properties of materials change due to nuclear transmutations is a major challenge for the design of structural components for a fusion power plant. In this study, by combining a first-principles matrix Hamiltonian approach with thermodynamic integration we investigate quasisteady state configurations of multi-component alloys, …
PreprintM. J. Lloyd A. J. London M. Gilbert C. S. Becquart C. Domain E. Martinez M. Moody P. A. J. Bagot D. Nguyen-Manh D.E. J. Armstrong
Tungsten is one the primary candidate materials for the high neutron flux, high temperature components of a future demonstrate fusion reactor. Despite this, there is a lack of data on W under fusion relevant neutron doses and irradiation temperatures. Transmutation reactions result in the production of Re and Os solute atoms, at a rate which is …
Preprint PurchaseM. J. Lloyd E. Martinez L. Messina D. Nguyen-Manh
In this study, radiation-induced precipitation of transmutation products is addressed via the development of a new solute and vacancy concentration dependant Ising model for the W-Re-Os system. This new model includes interactions between both Os and Re atoms, thus facilitating more representative simulations of transmutation in fusion reactor comp…
Preprint PublishedAlexander 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…
PreprintJ.E. Menard R. Majeski M. Ono N.N. Bakharev V.K. Gusev M. Gryaznevich D. Kingham S. McNamara P. Thomas K. Hanada J. Harrison B. Lloyd Y.S. Hwang B. Lipschultz H. Wilson Y. Nagayama Y. Ono Y. Takase M. Reinke K. Tobita Z. Gao F. Alladio R.J. Fonck
The spherical torus/tokamak (ST) is a potentially attractive configuration for narrowing scientific and technical gaps to a fusion demonstration power plant and as a more compact and/or modular fusion power source. Due to a reduced plasma surface area to volume ratio, the ST configuration offers the potential to access high power exhaust heat fl…
PreprintMatthew J. Lloyd Robert G. Abernethy Mark R. Gilbert Ian Griffiths Paul A. J. Bagot Duc Nguyen-Manh Michael P. Moody David E. J. Armstrong
High temperature, neutron irradiated single crystal tungsten, with a post irradiation composition of W-1.20±0.11at.%Re-0.11±0.05at.%Os-0.03±0.01at.%Ta was characterised using a combination of Atom Probe Tomography (APT) and Scanning Transmission Electron Microscopy (STEM). APT showed that within nanoscale clusters of Re/Os, the atomic density wa…
Preprint PublishedM.J. Lloyd R.G. Abernethy D.A.J. Armstrong P.A.J. Bagot M.P. Moody E. Martinez D. Nguyen-Manh
A viable fusion power station is reliant on the development of plasma facing materials that can withstand the combined effects of high temperature operation and high neutron doses. In this study we focus on W, the most promising candidate material. Re is the primary transmutation product and has been shown to induce embrittlement through cluster fo…
Preprint Published