Sean M. McDeavitt
Affiliations: | Texas A & M University, College Station, TX, United States |
Area:
Materials Science Engineering, Nuclear EngineeringGoogle:
"Sean McDeavitt"
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Publications
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| Ortega LH, Blamer B, Stern KM, et al. (2020) Thermal conductivity of uranium metal and uranium-zirconium alloys fabricated via powder metallurgy Journal of Nuclear Materials. 531: 151982 |
| Badry F, Brito R, Abdoelatef MG, et al. (2019) An Experimentally Validated Mesoscale Model of Thermal Conductivity of a UO 2 and BeO Composite Nuclear Fuel Jom. 71: 4829-4838 |
| Irukuvarghula S, Blamer B, Ahn S, et al. (2017) Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffraction Journal of Nuclear Materials. 497: 10-15 |
| Garcia CB, Brito RA, Ortega LH, et al. (2017) Manufacture of a UO 2 -Based Nuclear Fuel with Improved Thermal Conductivity with the Addition of BeO Metallurgical and Materials Transactions E. 4: 70-76 |
| Spencer KY, Sudderth L, Brito RA, et al. (2016) Sensitivity study for accident tolerant fuels: Property comparisons and behavior simulations in a simplified PWR to enable ATF development and design Nuclear Engineering and Design. 309: 197-212 |
| Irukuvarghula S, Ahn S, McDeavitt SM. (2016) Decomposition of the γ phase in as-cast and quenched U-Zr alloys Journal of Nuclear Materials. 473: 206-217 |
| Ortega LH, Blamer BJ, Evans JA, et al. (2016) Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U3 Si2) with increased uranium loading Journal of Nuclear Materials. 471: 116-121 |
| Ahn S, Irukuvarghula S, McDeavitt SM. (2016) Microstructure of α-U and δ-UZr2 phase uranium-zirconium alloys irradiated with 140-keV He+ ion-beam Journal of Alloys and Compounds. 681: 6-11 |
| Humrickhouse-Helmreich CJ, Corbin R, McDeavitt SM. (2014) Measurement of thermal diffusivity of depleted uranium metal microspheres Journal of Nuclear Materials. 446: 100-105 |
| Ahn S, Irukuvarghula S, McDeavitt SM. (2014) Thermophysical investigations of the uranium–zirconium alloy system Journal of Alloys and Compounds. 611: 355-362 |