Maria A. Okuniewski, Ph.D.
Affiliations: | 2008 | University of Illinois, Urbana-Champaign, Urbana-Champaign, IL |
Area:
Nuclear Engineering, Materials Science EngineeringGoogle:
"Maria Okuniewski"Parents
Sign in to add mentorJames F. Stubbins | grad student | 2008 | UIUC | |
(Irradiation-induced microstructural evolution and mechanical properties in iron with and without helium.) |
BETA: Related publications
See more...
Publications
You can help our author matching system! If you notice any publications incorrectly attributed to this author, please sign in and mark matches as correct or incorrect. |
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 |