Search Results - "Burke, M.G."

Advanced microstructural characterization of the intergranular oxidation of Alloy 600 by Bertali, G., Scenini, F., Burke, M.G.

“…•Alloy 600 is susceptible to intergranular oxidation in hydrogenated steam at 480°C.•It is demonstrated that GB migration occurs during intergranular…”
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Large volume serial section tomography by Xe Plasma FIB dual beam microscopy by Burnett, T.L., Kelley, R., Winiarski, B., Contreras, L., Daly, M., Gholinia, A., Burke, M.G., Withers, P.J.

“…Ga+ Focused Ion Beam-Scanning Electron Microscopes (FIB-SEM) have revolutionised the level of microstructural information that can be recovered in 3D by block…”
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Tracer study of pore initiation in anodic alumina formed in phosphoric acid by Baron-Wiecheć, A., Burke, M.G., Hashimoto, T., Liu, H., Skeldon, P., Thompson, G.E., Habazaki, H., Ganem, J.-J., Vickridge, I.C.

“…•Arsenic species are used as a tracer to investigate pore initiation in anodic alumina.•Arsenic species are shown to be immobile in anodic alumina during…”
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Solute precipitation on a screw dislocation and its effects on dislocation mobility in bcc Fe by Pascuet, M.I., Monnet, G., Bonny, G., Martínez, E., Lim, J.J.H., Burke, M.G., Malerba, L.

“…Reactor pressure vessel steels are well-known to harden and embrittle under neutron irradiation. The primary mechanism of radiation embrittlement for these…”
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High performance power handling in the absence of an H-mode edge in negative triangularity DIII-D plasmas by Scotti, F., Marinoni, A., McLean, A.G., Paz-Soldan, C., Thome, K.E., Zhao, M., Allen, S., Austin, M., Burke, M.G., Eldon, D., Fenstermacher, M., Hyatt, A., Lasnier, C.J., Leonard, A., Lore, J., Nelson, A.O., Osborne, T., Sauter, O., Truong, D., Van Zeeland, M.A., Wang, H.Q., Wilcox, R.

“…Abstract Experiments performed during strongly-shaped high-power diverted negative triangularity (NT) experiments in DIII-D achieved detached divertor…”
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The application of in situ analytical transmission electron microscopy to the study of preferential intergranular oxidation in Alloy 600 by Burke, M.G., Bertali, G., Prestat, E., Scenini, F., Haigh, S.J.

“…In situ analytical transmission electron microscopy (TEM) can provide a unique perspective on dynamic reactions in a variety of environments, including liquids…”
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Post-irradiation annealing of Ni–Mn–Si-enriched clusters in a neutron-irradiated RPV steel weld using Atom Probe Tomography by Styman, P.D., Hyde, J.M., Parfitt, D., Wilford, K., Burke, M.G., English, C.A., Efsing, P.

“…•Characterisation of high Ni neutron irradiated RPV surveillance samples at high fluence.•Post-irradiation annealing performed to give insight into the…”
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Formation of barrier-type anodic films on ZE41 magnesium alloy in a fluoride/glycerol electrolyte by Hernández-López, J.M., Němcová, A., Zhong, X.L., Liu, H., Arenas, M.A., Haigh, S.J., Burke, M.G., Skeldon, P., Thompson, G.E.

“…•Barrier anodic films formed on ZE41 Mg alloy in glycerol/fluoride electrolyte.•Films contain oxygen and fluorine species; formation ratio…”
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Measurement of size-dependent composition variations for gamma prime (γ′) precipitates in an advanced nickel-based superalloy by Chen, Y.Q., Slater, T.J.A., Lewis, E.A., Francis, E.M., Burke, M.G., Preuss, M., Haigh, S.J.

“…Energy-dispersive X-ray (EDX) spectroscopy in the scanning transmission electron microscope (STEM) has been used to demonstrate the presence of size-dependent…”
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Helical-centreline (BioMimics 3D) stent offers long term patency protection in patients with femoropopliteal disease by Caro, C.G, Zeller, T, Heraty, K.B, Burke, M.G, Gilson, P

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Atom probe tomography of reactor pressure vessel steels: An analysis of data integrity by Hyde, J.M., Burke, M.G., Gault, B., Saxey, D.Wf, Styman, P., Wilford, K.B., Williams, T.J.

“…In this work, the importance of optimising experimental conditions for the analysis of reactor pressure vessel (RPV) steels using atom probe tomography is…”
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Understanding the role of Diffusion Induced Grain Boundary Migration on the preferential intergranular oxidation behaviour of Alloy 600 via advanced microstructural characterization by Volpe, L., Burke, M.G., Scenini, F.

“…This present work introduces a new understanding of the precursors events to Stress Corrosion Cracking (SCC) initiation in nuclear power plant components,…”
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Correlation between Grain Boundary Migration and Stress Corrosion Cracking of Alloy 600 in Hydrogenated Steam by Volpe, L., Burke, M.G., Scenini, F.

“…Solution-annealed Alloy 600 samples were tested under active load conditions in a superheated low pressure H2-steam environment over a range of oxidising…”
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The effect of residual stress on the Preferential Intergranular Oxidation of Alloy 600 by Bertali, G., Scenini, F., Burke, M.G.

“…•Alloy 600 is susceptible to preferential intergranular oxidation in H2-steam at 480°C.•Residual tensile stresses enhance intergranular oxidation.•Correlation…”
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Effect of temperature on the preferential intergranular oxidation susceptibility of thermally-treated Alloy 600 by Volpe, L., Bertali, G., Scenini, F., Burke, M.G.

“…Thermally-treated Alloy 600 coupons were tested in pressurized water reactor simulated primary water at 320 °C and in high-pressure superheated steam at 400 °C…”
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Modelling the nucleation, growth and coarsening kinetics of γ″ (D022) precipitates in the Ni-base Alloy 625 by Moore, I.J., Burke, M.G., Palmiere, E.J.

“…Alloy 625 is susceptible to significant precipitation hardening through the formation of γ″ (D022-NbNi3) particles. These precipitates can form both during…”
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Stress corrosion crack initiation in filler metal 82 in oxygenated high-temperature water by Supornpaibul, N., Duff, J., Burke, M.G., Wang, Y., Scenini, F.

“…The Stress Corrosion Cracking (SCC) initiation in filler metal (FM) 82 was studied in oxygenated (O2) water at 288 °C. Post-test microstructural…”
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The intergranular oxidation susceptibility of thermally–treated Alloy 600 by Bertali, G., Scenini, F., Burke, M.G.

“…•Thermally-treated Alloy 600 is susceptible to intergranular oxidation in H2-steam at 480°C.•It is demonstrated that intergranular carbides are susceptible to…”
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Advanced microstructural characterization of transgranular Pb-caustic SCC in Alloy 690TT by Mazzei, G.B., Burke, M.G., Horner, D.A., Scenini, F.

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Lead-induced stress corrosion cracking (PbSCC) initiation in alloy 690TT in caustic environment by Mazzei, G.B., Burke, M.G., Horner, D.A., Scenini, F.

“…Pb-Caustic Stress Corrosion Cracking initiation was studied on Alloy 690TT at 315 °C. Advanced electron microscopy techniques revealed that cracking mainly…”
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