Projects
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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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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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