Projects
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NSUF 18-1525: Neutron Irradiation of Ga2O3 to Identify Native Point Defects
We propose to study the effect of forming gas (FG) annealing on the native...
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NSUF 18-1529: Correlation between In-situ TEM Observations of Radiation Damage of an Advanced Ferritic/Martensitic Alloy under Dual-Beam Ion Irradiation and its Mechanical Properties through In-situ Nanomechanical Testing
The objective of the work is to correlate the microstructure evolution...
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NSUF 18-1531: Microstructure Analysis of High Dose Neutron Irradiated Alloys
The promise for developing new, advanced nuclear reactor concepts that...
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NSUF 18-1532: Investigation of the synergistic effects of dual beam irradiation in an austenitic-ferritic duplex alloy
This project aims to (1) considerably improve the fidelity of ion irradiation...
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NSUF 18-1533: Investigation of fuel-cladding chemical interaction (FCCI) in irradiated U-Pu-Zr fuel
Fast reactor technology provides a path to transmute long-lived transuranic...
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NSUF 18-1535: Non-destructive X-ray computed tomography analysis of SiC composite tubes neutron-irradiated with and without a high radial heat flux
Silicon carbide (SiC) fiber-reinforced SiC matrix (SiC-SiC) composites are of...
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NSUF 18-1538: Electron microscopy characterization of fast reactor MOX joint oxyde-gaine (JOG)
The objective of this work is to evaluate the microstructure and chemical...
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NSUF 18-1539: Post-irradiation examinations of SiC composites neutron irradiated at 300°C to 30dpa
Silicon carbide (SiC) fiber-reinforced SiC matrix (SiC/SiC) composites...
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NSUF 18-1542: Microstructural investigation of hydride reorientation in zirconium based spent nuclear fuel cladding
The objective of this project is to investigate the influences of irradiation...
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NSUF 18-1545: Microstructural characterization of grain boundaries in Hastelloy N corroded in molten FLiBe salt under neutron irradiation
The Fluoride salt-cooled High-temperature Reactor (FHR) is being actively...
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NSUF 18-1547: Synchrotron XRD characterization of long range order in Ni-Cr alloys formed by isothermal aging or irradiation
The objectives of this work are to characterize the phase fraction of the...
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NSUF 18-1553: In-situ high temperature Transmission Electron Microscopy (TEM) of radiogenic He in high burnup fast reactor MOX
The fuel cross-section mount for the present study will be retrieved,...
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NSUF 18-1556: TEM Characterization of High Burnup MOX Fuel
MOX fuels offer the potential to power next generation nuclear reactors,...
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NSUF 18-1558: In-situ investigation of the Threshold Incubation Dose for the formation of c-component loops in additively manufactured and powder metallurgy rolled Ti-6Al-4V
In-situ TEM irradiation offers the unique capability to investigate the...
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NSUF 18-1561: Grain Size Effects on He and Xe behavior in UO2 and ThO2
It has been reported that radiation tolerance of materials increases as the...
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NSUF 18-1565: Characterization of Radiation Tolerance of Advanced Joining Techniques for Oxide Dispersion Strengthened Steels under Ion Irradiation
The objective of this work is to examine the effect of high damage levels of...
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NSUF 18-1566: In-situ TEM deformation of neutron irradiated FeCrAl alloys
The objectives of this in-situ TEM study on neutron irradiated FeCrAl-based...
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NSUF 18-1570: Phase Evolution of Uranium-Zirconium Alloys Under In-Situ TEM Heating
The binary uranium-zirconium (U-Zr) and the ternary uranium-plutonium-...
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NSUF 18-1584: Understanding the local atomic structure in variable composition, irradiated perovskites
Ceramics have varying uses across the nuclear industry, and have been...
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NSUF 18-1589: Irradiation Damage in (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C High-Entropy Ceramics
The objective of this project is examine the irradiation damage behavior in...
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