R.G. Abernethy J.S.K.-L. Gibson A. Giannattasio J.D. Murphy O. Wouters S. Bradnam L.W. Packer M.R. Gilbert M. Klimenkov M. Rieth H.-C. Schneider C.D. Hardie S.G. Roberts D.E.J. Armstrong
Only limited data exist on the effect of neutron irradiation on the brittle to ductile transition (BDT) in tungsten. This work investigates the increase in brittle to ductile transition temperature (BDTT) following neutron irradiation to 1.67 displacements per atom, using four-point bend tests over a range of temperatures (623 – 1173 K) and strai…
Preprint PublishedMatthew 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