Projects
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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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NSUF 18-1473: High Fluence Irradiation Testing of Fiber Optic Material Transmission
Rapid development and deployment of advanced nuclear fuels and materials will...
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NSUF 18-1474: Positron annihilation lifetime spectroscopy investigation of vacancy-related defects in room-temperature radiation detector material CdZnTe
The II-VI compound, cadmium zinc telluride (CdZnTe), is the most promising...
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NSUF 18-1484: EPMA Characterization of Actinide Redistribution and Fission Product Composition in MOX Fuels
The chemistry of MOX fuels and their secondary fission product phases can...
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NSUF 18-1491: Evaluating void swelling and microstructure evolution of additively manufactured HT9
The objective of this work is to evaluate the swelling characteristics of HT9...
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NSUF 18-1495: TEM investigation of irradiation, irradiation creep and thermal annealing effects in nuclear graphite
The Advanced Graphite Creep-1 (AGC-1) program was developed to qualify six...
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NSUF 18-1503: The study of local atomic structure and formation of ceramic phase in a simplified nuclear waste glassesl
This project aims to gain a fundamental insight into the stability of glass...
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NSUF 18-1509: Radiation tolerance of nanostructured amorphous/crystalline SiOC/Fe(Cr) nanocomposites
The objective of this project is to evaluate amorphous/crystalline...
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NSUF 18-1519: in-situ Transmission Electron Microscopy during Ion-Irradiation Studies of Cold Spray Coatings for Accident Tolerant Cladding
The goal of the proposed RTE research, led by the University of Wisconsin,...
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NSUF 18-1520: Investigation of the Tensile-Deformed Microstructure of a Neutron-Irradiated Type 316 Stainless Steel Specimen
TEM investigation will be performed on a tensile-deformed Type 316 stainless...
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