Search Results - "Anderoglu, Osman"

Application of small-scale testing for investigation of ion-beam-irradiated materials by Kiener, Daniel, Minor, Andrew M., Anderoglu, Osman, Wang, Yongqiang, Maloy, Stuart A., Hosemann, Peter

“…Small-scale testing techniques such as nanoindentation and micro-/nanocompression are promising methods for addressing mechanical properties of…”
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Characterization of 14YWT oxide dispersion strengthened structural materials under electrically-assisted tension by Jiang, Zilin, Zeng, Qiang, Anderoglu, Osman, Maloy, Stuart, Odette, G. Robert, Ehmann, Kornel F., Cao, Jian

“…In this study, we investigated the use of an electrically-assisted (EA) forming process to reduce the forming force of ODS ferritic steels. The effects of a…”
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Enhancing Shape Memory Response of Additively Manufactured Niti Shape Memory Alloys by Texturing and Post-Processing Heat Treatment by Saghaian, Sayed E., Nematollahi, Mohammadreza, Toker, Guher Pelin, Moghaddam, Narges Shayesteh, Saghaian, Sayed M., Radhakrishnan, Madhavan, Anderoglu, Osman, Elahinia, Mohammad, Karaca, Haluk

“…This study presents the shape memory behavior of Ni-rich NiTi shape memory alloy fabricated by Laser Powder Bed Fusion Additive Manufacturing (L-PBF-AM) before…”
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Correction to: Enhancing Shape Memory Response of Additively Manufactured Niti Shape Memory Alloys by Texturing and Post-Processing Heat Treatment by Saghaian, Sayed Ehsan, Nematollahi, Mohammadreza, Tuker, Guher Pelin, Moghadam, Narges Shayesteh, Saghaian, Sayed M., Radhakrishnan, Madhavan, Anderoglu, Osman, Elahinia, Mohammad, Karaca, Haluk

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The influence of ∑3 twin boundaries on the formation of radiation-induced defect clusters in nanotwinned Cu by Demkowicz, Michael J., Anderoglu, Osman, Zhang, Xinghang, Misra, Amit

“…We investigate the collective effect of a high volume fraction of ∑3 twin boundaries on the response of nanotwinned Cu to high dose He implantation near room…”
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Leveraging Neutronics to Monitor Mass Transfer Corrosion in Lead and Lead-Bismuth Cooled Reactors by Talaat, Khaled, Anderoglu, Osman

“…Corrosion phenomena in heavy liquid metal cooled reactors primarily result from dissolution and mass transfer of alloying elements such as nickel from the…”
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Corrosion in Heavy Liquid Metals for Energy Systems by Anderoglu, Osman, Marino, Alessandro, Hosemann, Peter

“…Heavy liquid metals (HLMs) such as molten Pb and lead bismuth eutectic (LBE) are being proposed as heat transport fluids in advanced nuclear and concentrated…”
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Microstructure evolution in MA956 neutron irradiated in ATR at 328 °C to 4.36 dpa by Zhang, Zhexian, Saleh, Tarik A., Maloy, Stuart A., Anderoglu, Osman

“…MA956 is an iron-chromium-aluminum (FeCrAl) based oxide dispersion strengthened (ODS) alloy produced by mechanical alloying. The alloy was irradiated in the…”
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The influence of thermomechanical treatment pathways on texture and mechanical properties in ARB Cu/Nb nanolaminates by Cheng, Justin Y., Radhakrishnan, Madhavan, Miller, Cody, Mier, Ryan, Vogel, Sven C., Savage, Daniel J., Carpenter, John S., Anderoglu, Osman, Mara, Nathan A.

“…Accumulative roll-bonded Cu/Nb nanolaminates (ARB Cu/Nb) possess high strength, thermal stability, and radiation tolerance arising from a high content of…”
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Design of specimen holders for flow accelerated corrosion experiments in molten lead with numerical evaluation of pressure losses by Talaat, Khaled, Hassan, Md Mehadi, Cakez, Cemal, Ghosh, Shuprio, Bohanon, Brandon, Woloshun, Keith, Unal, Cetin, Anderoglu, Osman

“…•A loop has been established to investigate structural material compatibility with molten Pb up to 700C.•Designs of specimen holders for flow accelerated…”
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Influence of the stacking sequence on the through-thickness Young’s moduli of fibrous composite laminates measured by nanoindentation by Xu, Luoyu Roy, Hassan, Md Mehadi, Anderoglu, Osman, Zhao, Kai, Flores, Mark

“…Previous approaches to measure the through-thickness Young’s modulus of a composite laminate often employed complicated specimens and test procedures, so very…”
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Effect of helium irradiation on Ti3AlC2 at 500°C by Patel, Maulik K., Tallman, Darin J., Valdez, James A., Aguiar, Jeffery, Anderoglu, Osman, Tang, Ming, Griggs, Justin, Fu, Engang, Wang, Yongqiang, Barsoum, Michel W.

“…We report herein, for the first time, the effects of high-fluence (2×1017 ionscm−2; 14at.%) helium irradiation of polycrystalline Ti3AlC2 samples at 500°C…”
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Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear Reactors by Anderoglu, Osman, Byun, Thak Sang, Toloczko, Mychailo, Maloy, Stuart A.

“…Ferritic/martensitic (F/M) steels are considered for core applications and pressure vessels in Generation IV reactors as well as first walls and blankets for…”
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Layer dissolution in accumulative roll bonded bulk Zr/Nb multilayers under heavy-ion irradiation by Radhakrishnan, M., Kombaiah, B., Bachhav, M.N., Nizolek, T.J., Wang, Y.Q., Knezevic, M., Mara, N., Anderoglu, O.

“…The heavy-ion irradiation behavior of bulk zirconium-niobium multilayered composites was investigated up to large doses. Multilayers with an average individual…”
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Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations by Aydogan, E., Almirall, N., Odette, G.R., Maloy, S.A., Anderoglu, O., Shao, L., Gigax, J.G., Price, L., Chen, D., Chen, T., Garner, F.A., Wu, Y., Wells, P., Lewandowski, J.J., Hoelzer, D.T.

“…A nanostructured ferritic alloy (NFA), 14YWT, was produced in the form of thin walled tubing. The stability of the nano-oxides (NOs) was determined under…”
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Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at ≈295 °C to ≈6.5 dpa by Maloy, S.A., Saleh, T.A., Anderoglu, O., Romero, T.J., Odette, G.R., Yamamoto, T., Li, S., Cole, J.I., Fielding, R.

“…Tensile test results at 25 and 300 °C on five 9-12Cr tempered martensitic steels and one 14Cr oxide dispersion strengthened alloy, that were side-by side…”
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Thermal annealing recovery of fracture toughness in HT9 steel after irradiation to high doses by Byun, Thak Sang, Baek, Jong-Hyuk, Anderoglu, Osman, Maloy, Stuart A., Toloczko, Mychailo B.

“…The HT9 ferritic/martensitic steel with a nominal chemistry of Fe(bal.)12%Cr1%MoVW has been used as a primary core material for fast fission reactors such as…”
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Irradiation-induced formation of a spinel phase at the FeCr/MgO interface by Xu, Yun, Yadav, Satyesh Kumar, Aguiar, Jeffery A., Anderoglu, Osman, Baldwin, Jon Kevin, Wang, Yongqiang, Misra, Amit, Luo, Hongmei, Uberuaga, Blas P., Li, Nan

“…Oxide dispersion strengthened ferritic/martensitic alloys have attracted significant attention for their potential uses in future nuclear reactors and storage…”
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Thermal annealing recovery of fracture toughness in HT9 steel after irradation to high doses by Byun, Thak Sang, Baek, Jong-Hyuk, Anderoglu, Osman, Maloy, Stuart A., Toloczko, Mychailo B.

“…The HT9 ferritic/martensitic steel with a nominal chemistry of Fe(bal.)–12%Cr–1%MoVW has been used as a primary core material for fast fission reactors such as…”
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The influence of Σ3 twin boundaries on the formation of radiation-induced defect clusters in nanotwinned Cu by Demkowicz, Michael J., Anderoglu, Osman, Zhang, Xinghang, Misra, Amit

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