Search Results - "OKUNIEWSKI, M. A"

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  1. 1

    High energy X-ray diffraction measurement of residual stresses in a monolithic aluminum clad uranium―10 wt% molybdenum fuel plate assembly by BROWN, D. W, OKUNIEWSKI, M. A, ALMER, J. D, BALOGH, L, CLAUSEN, B, OKASINSKI, J. S, RABIN, B. H

    Published in Journal of nuclear materials (01-10-2013)
    “…Residual stresses are expected in monolithic, aluminum clad uranium 10 wt% molybdenum (U-10Mo) nuclear fuel plates because of the large mismatch in thermal…”
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    Journal Article
  2. 2

    Thermotransport in γ(bcc) U–Zr alloys: A phase-field model study by Mohanty, R.R., Bush, J., Okuniewski, M.A., Sohn, Y.H.

    Published in Journal of nuclear materials (15-07-2011)
    “…Atomic transport in the presence of a temperature gradient, commonly known as thermotransport or the thermomigration phenomenon, was simulated for U–Zr alloys…”
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    Journal Article Conference Proceeding
  3. 3

    In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing by Williams, W. J., Okuniewski, M. A., Vogel, S. C., Zhang, J.

    Published in JOM (1989) (01-05-2020)
    “…A uranium-22.5 at.%zirconium (U-10 wt.%Zr) ingot was manufactured by traditional arc casting. The sample was characterized by high-pressure…”
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    Journal Article
  4. 4

    Elastic Properties of Rolled Uranium -- 10 wt.% Molybdenum Nuclear Fuel Foils by D. W. Brown, D. J. Alexander, K. D. Clarke, B. Clausen, M. A. Okuniewski, T. A. Sisneros

    Published in Scripta materialia (01-11-2013)
    “…In situ neutron diffraction data was collected during elastic loading of rolled foils of uranium-10 wt.% molybdenum bonded to a thin layer of zirconium…”
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    Journal Article
  5. 5

    Atomistic mechanisms of morphological evolution and segregation in U-Zr alloys by Moore, A.P., Deo, C., Baskes, M.I., Okuniewski, M.A.

    Published in Acta materialia (15-08-2016)
    “…In many metallic alloys, complex microstructures form as a consequence of local atomic ordering that depends on the processing path. This research uses an…”
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    Journal Article
  6. 6

    Understanding the uncertainty of interatomic potentials’ parameters and formalism by Moore, A.P., Deo, C., Baskes, M.I., Okuniewski, M.A., McDowell, D.L.

    Published in Computational materials science (01-01-2017)
    “…[Display omitted] •Sensitivity analyses are used to examine the uncertainty in MEAM potentials.•Trends and significance of parameters’ effects on properties…”
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    Journal Article
  7. 7

    Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates by Brown, D.W., Okuniewski, M.A., Sisneros, T.A., Clausen, B., Moore, G.A., Balogh, L.

    Published in Journal of nuclear materials (15-12-2016)
    “…Al clad U-10Mo fuel plates are being considered for conversion of several research reactors from high-enriched to low-enriched U fuel. Neutron diffraction…”
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    Journal Article
  8. 8

    Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction by Williams, W.J., Vogel, S.C., Okuniewski, M.A.

    Published in Journal of nuclear materials (01-06-2023)
    “…This work characterizes the crystallographic evolution of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) while cooling from equilibration, single phase γ-U-Zr,…”
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    Journal Article
  9. 9

    A modern reappraisal of the U-Zr phase diagram by Williams, W.J., Lund, J., García, R.E., Okuniewski, M.A.

    Published in Journal of nuclear materials (01-01-2025)
    “…•Optimized thermodynamic parameters and constructed U-Zr phase diagrams (PD) via ML.•Comparing historical PDs with experimental data identified a need for…”
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    Journal Article
  10. 10

    Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT) by Williams, W.J., Wachs, D.M., Okuniewski, M.A., van den Berghe, S.

    Published in Annals of nuclear energy (01-02-2020)
    “…•Identified four performance issues that may limit uranium-zirconium fuel lifetime.•Constituent redistribution and fuel swelling in uranium-zirconium were…”
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    Journal Article
  11. 11

    Atomistic modeling of high temperature uranium–zirconium alloy structure and thermodynamics by Moore, A.P., Beeler, B., Deo, C., Baskes, M.I., Okuniewski, M.A.

    Published in Journal of nuclear materials (01-12-2015)
    “…A semi-empirical Modified Embedded Atom Method (MEAM) potential is developed for application to the high temperature body-centered-cubic uranium–zirconium…”
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    Journal Article
  12. 12

    Neutron diffraction measurement of residual stresses in Al-clad U–10Mo fuel plates by Brown, D.W., Okuniewski, M.A., Clausen, B., Moore, G.A., Sisneros, T.A.

    Published in Journal of nuclear materials (01-06-2016)
    “…Neutron diffraction was used to determine residual stress in monolithic two Al-clad U 10 weight percent Mo mini-fuel plates and a full sized fuel plate. One…”
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    Journal Article
  13. 13

    Impurity migration and effects on vacancy formation enthalpy in polycrystalline depleted uranium by Lund, K.R., Lynn, K.G., Weber, M.H., Macchi, C., Somoza, A., Juan, A., Okuniewski, M.A.

    Published in Journal of nuclear materials (01-11-2015)
    “…We have used Doppler-broadening of the positron-electron annihilation radiation technique and VASP calculations to verify the previously reported vacancy…”
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    Journal Article
  14. 14

    Thermotransport in y(bcc) U–Zr alloys: A phase-field model study by R. R. Mohanty, J. Bush, M. A. Okuniewski, Y. H. Sohn

    Published in Journal of nuclear materials (01-07-2011)
    “…Atomic transport in the presence of a temperature gradient, commonly known as thermotransport or the thermomigration phenomenon, was simulated for U-Zr alloys…”
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    Journal Article
  15. 15

    Small-angle X-ray scattering measurements of helium-bubble formation in borosilicate glass by Terekhov, Alexander Y., Heuser, Brent J., Okuniewski, Maria A., Averback, Robert S., Seifert, Söenke, Jemian, Pete R.

    Published in Journal of applied crystallography (01-10-2006)
    “…Small‐angle X‐ray scattering (SAXS) measurements have been performed to study helium‐bubble formation in borosilicate glass. Helium was introduced by He+…”
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    Journal Article
  16. 16

    Positron annihilation spectroscopy of proton irradiated single crystal BCC iron by Okuniewski, Maria A., Wells, Doug P., Selim, Farida A., Maloy, Stuart A., James, Michael R., Stubbins, James F., Deo, Chaitanya S., Srivilliputhur, Srinivasan G., Baskes, Michael I.

    Published in Journal of nuclear materials (01-06-2006)
    “…Positron annihilation spectroscopy was used to analyze the open-volume defects created in single crystal, body-centered cubic iron irradiated with 1.0 MeV…”
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    Journal Article