Search Results - "Edmondson, Philip"

High temperature annealing of ion irradiated tungsten by Ferroni, Francesco, Yi, Xiaoou, Arakawa, Kazuto, Fitzgerald, Steven P., Edmondson, Philip D., Roberts, Steve G.

“…Transmission electron microscopy of high temperature annealing of pure tungsten irradiated by self-ions was conducted to elucidate microstructural and defect…”
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Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys by Sun, Zhiqian, Edmondson, Philip D., Yamamoto, Yukinori

“…The microstructures and mechanical properties of deformed and annealed Nb-containing FeCrAl alloys were investigated. Fine dispersion of Fe2Nb-type Laves phase…”
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Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of Low-Cr ODS FeCrAl alloys by Massey, Caleb P., Dryepondt, Sebastien N., Edmondson, Philip D., Terrani, Kurt A., Zinkle, Steven J.

“…Low-chromium (<10%Cr) high strength oxide dispersion strengthened (ODS) FeCrAl alloys are considered promising candidates for accident tolerant fuel cladding…”
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Site specific, high-resolution characterisation of porosity in graphite using FIB-SEM tomography by Arregui-Mena, José David, Edmondson, Philip D., Campbell, Anne A., Katoh, Yutai

“…Graphite is used as a moderator of fast neutrons in some types of nuclear reactors and for other industrial applications. The influence of smaller pores on the…”
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The effect of electronic energy loss on irradiation-induced grain growth in nanocrystalline oxides by Zhang, Yanwen, Aidhy, Dilpuneet S, Varga, Tamas, Moll, Sandra, Edmondson, Philip D, Namavar, Fereydoon, Jin, Ke, Ostrouchov, Christopher N, Weber, William J

“…Grain growth of nanocrystalline materials is generally thermally activated, but can also be driven by irradiation at much lower temperature. In nanocrystalline…”
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Nanoprecipitates to Enhance Radiation Tolerance in High-Entropy Alloys by Kombaiah, Boopathy, Zhou, Yufan, Jin, Ke, Manzoor, Anus, Poplawsky, Jonathan D., Aguiar, Jeffery A., Bei, Hongbin, Aidhy, Dilpuneet S., Edmondson, Philip D., Zhang, Yanwen

“…The growth of advanced energy technologies for power generation is enabled by the design, development, and integration of structural materials that can…”
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Development of mesopores in superfine grain graphite neutron-irradiated at high fluence by Contescu, Cristian I., Arregui-Mena, José D., Campbell, Anne A., Edmondson, Philip D., Gallego, Nidia C., Takizawa, Kentaro, Katoh, Yutai

“…Microstructural changes induced by neutron irradiation of superfine grain graphite G347A (Tokai Carbon, Japan) were examined by nitrogen adsorption at 77 K and…”
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Radiation induced amorphization of carbides in additively manufactured and conventional ferritic-martensitic steels: In-situ experiments on extraction replicas by Bhattacharya, Arunodaya, Levine, Samara M., Zinkle, Steven J., Chen, Wei-Ying, Baldo, Peter, Parish, Chad M., Edmondson, Philip D.

“…•In-situ irradiations performed on nanoprecipitates in Eurofer97 and AM-Grade91.•The M23C6 carbides are highly susceptible to radiation induced…”
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Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation by Massey, Caleb P., Zhang, Dalong, Briggs, Samuel A., Edmondson, Philip D., Yamamoto, Yukinori, Gussev, Maxim N., Field, Kevin G.

“…FeCrAl alloys have been extensively investigated over the past decade as a candidate material for accident-tolerant fuel cladding in light water reactors. This…”
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The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys by Massey, Caleb, Edmondson, Philip, Unocic, Kinga, Yang, Ying, Dryepondt, Sebastien N., Kini, Anoop, Gault, Baptiste, Terrani, Kurt, Zinkle, Steven J.

“…Oxide dispersion strengthened (ODS) FeCrAl alloys are promising candidate materials for advanced nuclear reactor applications requiring high-temperature…”
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Microstructural investigation of an extruded austenitic oxide dispersion strengthened steel containing a carbon-containing process control agent by Gräning, Tim, Rieth, Michael, Hoffmann, Jan, Seils, Sascha, Edmondson, Philip D., Möslang, Anton

“…The adhesion of austenitic oxide dispersion strengthened (ODS) steel during mechanical alloying and a decreased powder production yield can be overcome by the…”
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Investigating sluggish diffusion in a concentrated solid solution alloy using ion irradiation with in situ TEM by Tunes, Matheus A., Le, Hoang, Greaves, Graeme, Schön, Cláudio G., Bei, Hongbin, Zhang, Yanwen, Edmondson, Philip D., Donnelly, Stephen E.

“…Concentrated solid solution alloys (CSAs) – including high entropy alloys – are known for their remarkable mechanical and corrosion resistances with superior…”
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Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy by Zhang, Dalong, Briggs, Samuel A., Edmondson, Philip D., Gussev, Maxim N., Howard, Richard H., Field, Kevin G.

“…An advanced accident-tolerant FeCrAl alloy, C35 M (Fe–13Cr–10Al–1Mo, at %), and its laser-fusion weldments were studied after neutron irradiation up to 1.8 dpa…”
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Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review by Bhattacharya, Arunodaya, Zinkle, Steven J, Henry, Jean, Levine, Samara M, Edmondson, Philip D, Gilbert, Mark R, Tanigawa, Hiroyasu, Kessel, Charles E

“…Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are the most promising candidates for fusion first-wall/blanket…”
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The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys by Massey, Caleb P., Edmondson, Philip D., Unocic, Kinga A., Yang, Ying, Dryepondt, Sebastien N., Kini, Anoop, Gault, Baptiste, Terrani, Kurt A., Zinkle, Steven J.

“…Oxide dispersion strengthened (ODS) FeCrAl alloys are promising candidate materials for advanced nuclear reactor applications requiring high-temperature…”
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Energetic particle irradiation study of TiN coatings: are these films appropriate for accident tolerant fuels? by Tunes, Matheus A., da Silva, Felipe C., Camara, Osmane, Schön, Claudio G., Sagás, Julio C., Fontana, Luis C., Donnelly, Stephen E., Greaves, Graeme, Edmondson, Philip D.

“…Coating nuclear fuel cladding alloys with hard thin films has been considered as an innovative solution to increase the safety of nuclear reactors, in…”
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Corrigendum to “Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation” by Massey, Caleb P., Zhang, Dalong, Briggs, Samuel A., Edmondson, Philip D., Yamamoto, Yukinori, Gussev, Maxim N., Littrell, Kenneth C., Field, Kevin G.

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Electron tomography of unirradiated and irradiated nuclear graphite by Arregui-Mena, José David, Cullen, David A., Worth, Robert N., Venkatakrishnan, Singanallur V., Jordan, Matthew S.L., Ward, Michael, Parish, Chad M., Gallego, Nidia, Katoh, Yutai, Edmondson, Philip D., Tzelepi, Nassia

“…Graphite is the moderator material of several Generation IV nuclear reactor concepts, as well as the British Advanced Gas-cooled Reactors (AGR). Porosity can…”
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Characterisation of the spatial variability of material properties of Gilsocarbon and NBG-18 using random fields by Arregui-Mena, José David, Edmondson, Philip D., Margetts, Lee, Griffiths, D.V., Windes, William E., Carroll, Mark, Mummery, Paul M.

“…Graphite is a candidate material for Generation IV concepts and is used as a moderator in Advanced Gas-cooled Reactors (AGR) in the UK. Spatial material…”
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Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration by Massey, Caleb P., Hoelzer, David T., Seibert, Rachel L., Edmondson, Philip D., Kini, Anoop, Gault, Baptiste, Terrani, Kurt A., Zinkle, Steven J.

“…Fast reactor fuel cladding candidate materials require proficiency in extreme environments consisting of high temperatures and irradiation doses in excess of…”
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