Projects
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NSUF 26-5633: Exploring Irradiation Effects on Laser Powder Bed Fusion Produced Stainless Steel 316L
Localized stresses are known to have a profound effect on the mechanical...
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NSUF 26-5639: Fast-Neutron Irradiation of SiC LGAD/PiN Radiation Detectors and their layer-equivalent bulk material analogs.
We will conduct fast neutron irradiation studies on self-fabricated SiC PiN...
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NSUF 26-5643: Radiation Examination of Novel Ni-based alloy (Ni-Cr-Mo-W-(Ti/Al)) for Molten Chloride Fast Reactor Structural Applications
Molten chloride salts are promising high-temperature (400–950 °C) heat...
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NSUF 26-5644: Nanoscale feature stability and irradiation response in GRX-810 at elevated temperatures
This project aims to determine the high-temperature irradiation stability...
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NSUF 26-5647: Quantifying Hydrogen Defects in irradiated Zirconium Alloys
In this RTE, we propose leveraging the post-irradiation examination...
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NSUF 26-5649: SEM and TEM Characterization of Phase Reverted U-10Mo Alloys Neutron Irradiated to Mid Dose Sub-Eutectoid Temperatures
U-Mo fuels are promising candidates for advanced reactors due to their fuel...
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NSUF 26-5651: The Role of Temporal Temperature Gradients on Microstructure Evolution using Proton Irradiations
Nearly all neutron irradiation experiments for domestic materials...
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NSUF 26-5654: Evaluation of Interconnected Porosity in an Irradiated Annular U-10Zr Fuel
The goal of this project is to investigate the 3D morphology and porosity...
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NSUF 26-5655: TEM characterization of uranium secondary phases at the contact interface between UO2 fuel and Zircaloy-4 cladding under hydrothermal conditions
Hydrothermal corrosion experiments of UO2 in contact with Zircaloy-4 cladding...
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NSUF 26-5661: Evaluation of the Mechanical Properties of Phases in an Annular U-10Zr Irradiated Fuel
The goal of this project is to investigate the local mechanical properties of...
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NSUF 26-5662: Synchrotron X-ray Diffraction and Computed Tomography of Irradiated TRISO Fuel
This project aims to quantify uranium carbide consumption and spatial phase...
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NSUF 26-5663: Probing Hydrogen Embrittlement Mechanisms in Neutron-Irradiated RAFM Steel F82H
A neutron-irradiated (327 °C, 2.14 dpa) F82H Disk Multi-purpose Coupon (DMC)...
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NSUF 26-5666: Identifying the Roles of Irradiation and Stress in Dislocation-Mediated Grain Subdivision
High burnup structure (HBS) formation in nuclear fuels results from...
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NSUF 26-5670: Effect of Extrusion Temperature on Mechanical Property Evolution for FeCrAl-ODS Alloys Following Neutron Irradiation at Liquid Metal Fast Reactor Operating Temperatures
This RTE aims to investigate the difference in mechanical properties of...
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NSUF 26-5680: High-Resolution Microscopy of Uranium Mononitride MiniFuel to Quantify Lower-Length-Scale Parameters
Uranium mononitride (UN) is a promising fuel for advanced reactor concepts...
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NSUF 26-5684: Irradiation temperature-dependence of the mechanical properties of low-dpa MA956 from shear-punch and microhardness testing
The primary deliverables are empirical temperature-dependent correlations of...
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NSUF 26-5686: High Resolution Thermal Conductivity Study of ATR Irradiated YHx
Yttrium hydride (YHₓ) is a promising material for use in advanced nuclear...
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NSUF 26-5687: Irradiation tolerance and surface-layer stability of plasma-nitrided SS316H
This experiment aims to evaluate the effects of a plasma-nitrided surface...
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NSUF 26-5689: Radiation Tolerance and Microstructural Evolution in Solid-State-Processed High-Entropy Alloys
Structural materials for new-generation nuclear reactor designs must...
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NSUF 26-5699: In situ dual beam irradiation on additively manufactured T91 ODS steel
This project aims to elucidate irradiation-induced microstructural evolution...
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