Search Results - "OKUNIEWSKI, M. A"
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High energy X-ray diffraction measurement of residual stresses in a monolithic aluminum clad uranium―10 wt% molybdenum fuel plate assembly
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
Thermotransport in γ(bcc) U–Zr alloys: A phase-field model study
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
In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing
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
Elastic Properties of Rolled Uranium -- 10 wt.% Molybdenum Nuclear Fuel Foils
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
Atomistic mechanisms of morphological evolution and segregation in U-Zr alloys
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
Understanding the uncertainty of interatomic potentials’ parameters and formalism
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
Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates
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
Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction
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
A modern reappraisal of the U-Zr phase diagram
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
Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT)
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
Atomistic modeling of high temperature uranium–zirconium alloy structure and thermodynamics
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
Neutron diffraction measurement of residual stresses in Al-clad U–10Mo fuel plates
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
Impurity migration and effects on vacancy formation enthalpy in polycrystalline depleted uranium
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
Thermotransport in y(bcc) U–Zr alloys: A phase-field model study
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
Small-angle X-ray scattering measurements of helium-bubble formation in borosilicate glass
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
Positron annihilation spectroscopy of proton irradiated single crystal BCC iron
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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