Mohamed Elbakhshwan

Profile Information
Publications:
"In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation" Michael Moorehead, Calvin Parkin, Mohamed Elbakhshwan, Jing Hu, Wei-Ying Chen, Meimei Li, Lingfeng He, Kumar Sridharan, Adrien Couet, Acta Materialia Vol. 198 2020 85-99 Link
This study characterizes the microstructural evolution of single-phase complex concentrated solid- solution alloy (CSA) compositions under heavy ion irradiation with the goal of evaluating mecha- nisms for CSA radiation tolerance in advanced fission systems. Three such alloys, Cr 18 Fe 27 Mn 27 Ni 28 , Cr 15 Fe 35 Mn 15 Ni 35 , and equimolar NbTaTiV, along with reference materials (pure Ni and E90 for the Cr- FeMnNi family and pure V for NbTaTiV) were irradiated at 50 K and 773 K with 1 MeV Kr ++ ions to vari- ous levels of displacements per atom (dpa) using in-situ transmission electron microscopy. Cryogenic irra- diation resulted in small defect clusters and faulted dislocation loops as large as 12 nm in face-centered cubic (FCC) CSAs. With thermal diffusion suppressed at cryogenic temperatures, defect densities were lower in all CSAs than in their less compositionally complex reference materials indicating that point defect production is reduced during the displacement cascade stage. High temperature irradiation of the two FCC CSA resulted in the formation of interstitial dislocation loops which by 2 dpa grew to an average size of 27 nm in Cr 18 Fe 27 Mn 27 Ni 28 and 10 nm in Cr 15 Fe 35 Mn 15 Ni 35 . This difference in loop growth kinet- ics was attributed to the difference in Mn-content due to its effect on the nucleation rate by increasing vacancy mobility or reducing the stacking-fault energy.#171118
Presentations:
"The Effect of Photon Irradiation on the Corrosion of Zirconium Alloys" Adrien Couet, Yalong He, Kurt Terrani, Samuel Armson, Michael Preuss, Taeho Kim, Mohamed Elbakhshwan, Li He, The 19th International Symposium on Zirconium in the Nuclear Industry May 20-23, (2019)
Additional Publications:
"High-temperature annealing of proton irradiated beryllium - A dilatometry-based study" Mohamed Elbakhshwan, Zhong Zhong, Sanjit Ghose, Ilyas Savkliyildiz, Nikolaos Simos, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.04.001 · EID: 2-s2.0-84966447056
"Mechanical properties of UO2 thin films under heavy ion irradiation using nanoindentation and finite element modeling" Yinbin Miao, James F. Stubbins, Brent J. Heuser, Mohamed S. Elbakhshwan, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.07.047 · EID: 2-s2.0-84979782461
"Proton irradiation effects on beryllium – A macroscopic assessment" Mohamed Elbakhshwan, Zhong Zhong, Fernando Camino, Nikolaos Simos, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.06.048 · EID: 2-s2.0-84979523660
"Sample environment for in situ synchrotron corrosion studies of materials in extreme environments" Simerjeet K. Gill, Arthur T. Motta, Randy Weidner, Thomas Anderson, Lynne E. Ecker, Mohamed S. Elbakhshwan, [2016] Review of Scientific Instruments · DOI: 10.1063/1.4964101 · EID: 2-s2.0-84993978004

A new in situ sample environment has been designed and developed to study the interfacial interactions of nuclear cladding alloys with high temperature steam. The sample environment is particularly optimized for synchrotron X-ray diffraction studies for in situ structural analysis. The sample environment is highly corrosion resistant and can be readily adapted for steam environments. The in situ sample environment design complies with G2 ASTM standards for studying corrosion in zirconium and its alloys and offers remote temperature and pressure monitoring during the in situ data collection. The use of the in situ sample environment is exemplified by monitoring the oxidation of metallic zirconium during exposure to steam at 350 °C. The in situ sample environment provides a powerful tool for fundamental understanding of corrosion mechanisms by elucidating the substoichiometric oxide phases formed during the early stages of corrosion, which can provide a better understanding of the oxidation process.

"X-ray diffraction studies of 145 MeV proton-irradiated AlBeMet 162" Kirk T. McDonald, Sanjit Ghose, Zhong Zhong, Nikolaos Simos, Mohamed Elbakhshwan, [2016] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2016.05.002 · EID: 2-s2.0-84980332204
"Oxidation mitigation of zircaloy in high temperature steam via FeCrAI coatings" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84904633283
"Determination of UO2 thin films mechanical properties under heavy ion irradiation using nano-indentation and finite element modeling" [2013] Transactions of the American Nuclear Society · EID: 2-s2.0-84902495726
"Epitaxial growth of single crystal uranium oxide thin films on TiO 2, Al2O3, YSZ, ZnO and NdGaO3 substrates" [2013] Transactions of the American Nuclear Society · EID: 2-s2.0-84902479164
"Mechanical properties of zirconium hydrides using microhardness and nanoindentation" [2013] Transactions of the American Nuclear Society · EID: 2-s2.0-84902505731
"Characterization of single crystal uranium-oxide thin films grown via reactive-gas magnetron sputtering on yttria-stabilized zirconia and sapphire" Brent J. Heuser, Mohamed S. Elbakhshwan, Xiaochun Han, David J. Gennardo, Harrison K. Pappas, Hyunsu Ju, Melissa M. Strehle, [2012] Thin Solid Films · DOI: 10.1016/j.tsf.2012.04.022 · EID: 2-s2.0-84861813995
"Study the mechanical properties of thin films, single crystals of uranium dioxide using nanoindentation" [2012] Transactions of the American Nuclear Society · EID: 2-s2.0-84876376631
"Irradiation effects in UO2 and CeO2" [2010] Transactions of the American Nuclear Society · EID: 2-s2.0-79551656776
"Sputtering system capability for growth of uranium oxides and U xNd1-xO2 thin films" [2010] Transactions of the American Nuclear Society · EID: 2-s2.0-84875683407
Source: ORCID/CrossRef using DOI