Projects
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NSUF 17-944: Pre-characterization of DISECT UMo fuel samples
Nuclear low-enriched uranium based fuels with a high uranium density are...
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NSUF 17-950: SEM, EBSD, and TEM Investigation of Irradiated Austenitic Stainless Steel Weldment
As the existing light water reactor (LWR) fleet ages, the weldability of...
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NSUF 17-951: Performance of Nanocrystalline and Ultrafine Tungsten Under Irradiation and Mechanical Extremes
Performance of Nanocrystalline and Ultrafine Tungsten Under Irradiation and...
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NSUF 17-952: Atom Probe Tomography Study of Neutron Irradiated U-Mo Fuel
U–7-10 wt% Mo based fuel has been developed for application in high...
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NSUF 17-953: Post Irradiation Examination of Fiber Optic Temperature Sensors for In-Pile Temperature Monitor and Control for Advanced Test Reactor
The goal of this study is to investigate the radiation stability of fiber...
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NSUF 17-954: Study of nanocluster stability in neutron- and ion-irradiated ODS FeCrAl alloys
The objective of this project is to compare the resulting microstructures...
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NSUF 17-955: Hydrogen Analysis and Oxide Characterization of Reactor Irradiated Zr-Nb Alloy
The proposed post-irradiation examination (PIE) activity will evaluate the...
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NSUF 17-957: Fission Gas Behavior and Fuel Swelling of Accident Tolerant U3Si2 Fuels by Ion Beam Irradiation
U3Si2 fuel is the leading candidate of the accident tolerant fuels (ATFs),...
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NSUF 17-960: Changes on viscoelastic behavior, morphology and chemical structure of gamma irradiated calcium silicate hydrates to 0.96MGy with respect to non-irradiated samples
The proposed project objectives are to study the changes in viscoelastic...
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NSUF 17-961: Nano-precipitate Response to Neutron Irradiation in Model ODS FeCrAl Alloy 125YF
The primary objective of this project is to investigate the response of nano-...
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NSUF 17-968: Post-irradiation characterization of ion irradiation damage in Ti-6Al-4V and CP-Ti : Influence of the microstructure and temperature
Due to their high specific strength, good fatigue and creep properties,...
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NSUF 17-969: TEM investigation of radiation damage of ferrite in CF-3
CF-3 has been systematically studied under neutron irradiation on the ferrite...
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NSUF 17-971: The in-situ observation of radiation resistance mechanism in metal-1D/2D nanocomposites for structural material and fuel cladding of next generation reactors
The objective of this project is to reveal the underlying mechanism of the...
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NSUF 17-974: In situ TEM Study of the Ion Irradiation Damage on Hydrides in a Zirconium Alloy for Nuclear Fuel Cladding
The objective of this study is to investigate the ion irradiation damage in...
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NSUF 17-978: Micromechanical properties of interfacial elements in advanced SiC composite and its environmentally protective coatings
Silicon carbide (SiC) has been demonstrated as a highly capable engineering...
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NSUF 17-981: Quantitative assessment of the role of interfaces and grain boundaries in the development of radiation tolerant nuclear materials
Grain boundaries (GBs) are known as effective sinks for point defects created...
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NSUF 17-CINR-12527: Additive manufacturing of thermal sensors for in-pile thermal conductivity measurement
The goal of this project is to develop and demonstrate an additive...
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NSUF 17-CINR-12797: In-Situ Ion Irradiation to Add Irradiation Assisted Grain Growth to the MARMOT Tool
In this project, we will add the capability to model irradiation assisted...
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NSUF 17-CINR-12849: Simulation of Radiation and Thermal Effects in Advanced Cladding Materials
The motivation of the proposed work is to understand the dynamic radiation...
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NSUF 17-CINR-12985: Irradiation, Transient Testing and Post Irradiation Examination of Ultra High Burnup Fuel
This project is intended to generate sufficient test data to inform industry...
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