Projects
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NSUF 18-1396: Microstructural 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 18-1400: Characterization and modeling of secondary phase evolution in an irradiated Zr-1.0Nb alloy
The objective of this project is to characterize the solute nanocluster...
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NSUF 18-1403: Nanostructuring to enhance irradiation tolerance of ferritic/martensitic Grade 91 steels
F/M steels such as Grade 91 are leading fuel cladding and structural...
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NSUF 18-1405: In-situ TEM study of radiation and oxidation tolerance of MAX-phase-like materials
This project aims to understand the fundamental mechanism of the...
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NSUF 18-1412: Irradiated Microstructure Evolution in Cast Compared to PM-HIP Alloy 625
The objective of this study is to determine the influence of processing...
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NSUF 18-1424: Active Irradiation Testing of Temperature Sensing Capability of Clad Sapphire Optical Fibers with Type 2 Bragg Gratings using Optical Backscatter Reflectometry
We propose active irradiation testing of the temperature sensing capability...
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NSUF 18-1428: Microstructural characterization of transmutation nitride fuels for fast reactors
Transmutation nitride fuels by incorporating 3 minor actinides (Am, Np, and...
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NSUF 18-1433: A comparative study of the radiation response of Fe–12Cr, Fe–14Cr, Fe–19Cr model alloys and a Fe–14Cr ODS alloy
The objective of this program is to investigate the neutron radiation...
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NSUF 18-1434: Study on defect evolution and stability of Y-Ti-O nano-oxides in 14YWT alloys under heavy ion irradiation
Next generation fast spectrum reactors require structural materials that can...
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NSUF 18-1435: Determining Annealing Kinetics of SiC to Enable in LWR Accident Modeling
Silicon carbide composite has been discussed for more than a decade as a...
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NSUF 18-1437: In-Situ Phase Analysis of Phase Transitions in U-(6, 10, 20, 30) wt%Zr Fresh Fuels.
Understanding the microstructural evolution of U-Zr samples, including phase...
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NSUF 18-1441: Effects of Welding on Radiation-Enhanced Precipitation in FeCrAl Alloys
The objective of this project is to investigate the distribution of solute...
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NSUF 18-1452: High temperature in-situ small-scale mechanical testing of fast reactor mixed oxide (MOX) pins.
The main objective of this project is the determination of hardness, elastic...
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NSUF 18-1453: Electron Tomography Characterisation of Porosity in IG-110 and NBG-17 Nuclear Graphite Grades
Graphite is the moderator material of some Generation IV reactors concepts...
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NSUF 18-1455: Novel Microstructure Characterization of Pre-Hydrided ZIRLO® at Low Neutron Doses
Hydride precipitation is one of the major embrittling mechanisms which is...
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NSUF 18-1457: Microstructural Modifications in U-10Zr Irradiated by High-Energy Xe Ions
Gaseous fission products such as Xe and Kr form bubbles within nuclear fuel...
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NSUF 18-1459: Post-irradiation Piezoelectric Property Characterization of Radiation-Tolerant Piezoelectric Materials
The objective of this research is to quantify the dielectric and...
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NSUF 18-1464: Radiation Stability Study on Nuclear Waste Materials
Radiation damage and decay heat are significant issues for nuclear waste and...
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NSUF 18-1469: Investigation of neutron irradiation effects on Zr based bulk metallic glass (BMG) via advanced in situ mechanical testing and microstructural analysis.
Recently, Zr based BMGs have been reported to have properties that are...
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NSUF 18-1471: Controlling the kinetics of radiation induced crystallization in nanoceramics by doping
Light water systems have been the leading technology in the nuclear industry...
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