Maria A. Okuniewski, Ph.D.

Affiliations: 
2008 University of Illinois, Urbana-Champaign, Urbana-Champaign, IL 
Area:
Nuclear Engineering, Materials Science Engineering
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"Maria Okuniewski"

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James F. Stubbins grad student 2008 UIUC
 (Irradiation-induced microstructural evolution and mechanical properties in iron with and without helium.)
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Publications

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Wen D, Chang C, Matsunaga S, et al. (2020) Structure and tensile properties of Mx(MnFeCoNi)100-x solid solution strengthened high entropy alloys Materialia. 9: 100539
Thomas J, Bengoa AF, Nori ST, et al. (2020) The application of synchrotron micro-computed tomography to characterize the three-dimensional microstructure in irradiated nuclear fuel Journal of Nuclear Materials. 537: 152161
Williams WJ, Wachs DM, Okuniewski MA, et al. (2020) Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT) Annals of Nuclear Energy. 136: 107016
Beeler B, Zhang Y, Okuniewski M, et al. (2018) Calculation of the displacement energy of α and γ uranium Journal of Nuclear Materials. 508: 181-194
Biswas S, Schwen D, Wang H, et al. (2018) Phase field modeling of sintering: Role of grain orientation and anisotropic properties Computational Materials Science. 148: 307-319
Moore AP, Deo C, Baskes MI, et al. (2017) Understanding the uncertainty of interatomic potentials’ parameters and formalism Computational Materials Science. 126: 308-320
Brown DW, Okuniewski MA, Sisneros TA, et al. (2016) Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates Journal of Nuclear Materials. 482: 63-74
Moore AP, Deo C, Baskes MI, et al. (2016) Atomistic mechanisms of morphological evolution and segregation in U-Zr alloys Acta Materialia. 115: 178-188
Chen WY, Miao Y, Gan J, et al. (2016) Neutron irradiation effects in Fe and Fe-Cr at 300 °c Acta Materialia. 111: 407-416
Moore AP, Beeler B, Deo C, et al. (2015) Atomistic modeling of high temperature uranium-zirconium alloy structure and thermodynamics Journal of Nuclear Materials. 467: 802-819
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