Projects
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NSUF 25-5165: Interplay of Nanoscale Heterogeneities and Radiation Damage in Compositionally Complex Alloys
Non-dilute multicomponent alloys, or compositionally complex alloys (CCAs),...
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NSUF 25-5165: Interplay of Nanoscale Heterogeneities and Radiation Damage in Compositionally Complex Alloys አሳይ -
NSUF 25-5202: Atom probe tomography of HT-9 to evaluate the effect of neutron irradiation temperature, alloying element and heat treatment
Ferritic-martensitic steels are being considered as candidate structural...
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NSUF 25-5202: Atom probe tomography of HT-9 to evaluate the effect of neutron irradiation temperature, alloying element and heat treatment አሳይ -
NSUF 25-5206: Elucidating the Role of Polymeric Coatings in Optical Fiber Sensors under Neutron Irradiation
This project aims to investigate the hypothesis that polymeric coatings on...
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NSUF 25-5206: Elucidating the Role of Polymeric Coatings in Optical Fiber Sensors under Neutron Irradiation አሳይ -
NSUF 25-5208: Investigating Ultraviolet Sensitive Avalanche Photodiodes by Ion Implantation in 4H-Silicon Carbide for High Temperature Sensing
High temperature and radiation are an ever-present challenge faced when...
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NSUF 25-5208: Investigating Ultraviolet Sensitive Avalanche Photodiodes by Ion Implantation in 4H-Silicon Carbide for High Temperature Sensing አሳይ -
NSUF 25-5218: Elevated temperature gamma irradiation of optical fibers sensors for spent nuclear fuel dry cask storage system canister structural health monitoring applications
Methods to Be Employed The project will assess and demonstrate feasibility...
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NSUF 25-5218: Elevated temperature gamma irradiation of optical fibers sensors for spent nuclear fuel dry cask storage system canister structural health monitoring applications አሳይ -
NSUF 25-5224: High resolution characterization of U3Si2 fuel rodlets using Transmission Electron Microscopy and Atom Probe Tomography
U3Si2 has received attention due to its larger thermal neutron absorption...
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NSUF 25-5224: High resolution characterization of U3Si2 fuel rodlets using Transmission Electron Microscopy and Atom Probe Tomography አሳይ -
NSUF 25-5225: Mechanical Properties Characterization and Atom Probe Tomography Preparation of BOR60 Neutron Irradiated T91 Steel Samples for Surrogate Ion-Irradiation Comparison
T91 is a ferritic/martensitic (F/M) steel being investigated as a promising...
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NSUF 25-5225: Mechanical Properties Characterization and Atom Probe Tomography Preparation of BOR60 Neutron Irradiated T91 Steel Samples for Surrogate Ion-Irradiation Comparison አሳይ -
NSUF 25-5227: Assessing the Irradiation-Assisted Hydrothermal Degradation of Bulk GB Engineered SiC
This project will assess the effectiveness of the GB engineering approach in...
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NSUF 25-5227: Assessing the Irradiation-Assisted Hydrothermal Degradation of Bulk GB Engineered SiC አሳይ -
NSUF 25-5230: Determination of Swelling Across Temperatures in Vanadium Alloys Without Transmutation
Vanadium alloys were developed as candidate alloys for cladding materials of...
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NSUF 25-5230: Determination of Swelling Across Temperatures in Vanadium Alloys Without Transmutation አሳይ -
NSUF 25-5231: Effect of irradiation on 3D printed magnetostrictive materials
Magnetostrictive materials deform in response to a magnetic field and exhibit...
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NSUF 25-5231: Effect of irradiation on 3D printed magnetostrictive materials አሳይ -
NSUF 25-5237: Property measurement of LiF-NaF-ZrF4-UF4
For this RTE, the melting temperature of the salt will be measured using a...
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NSUF 25-5237: Property measurement of LiF-NaF-ZrF4-UF4 አሳይ -
NSUF 25-5238: Improved In-reactor Performance of SiC by n-Doping with Phosphorus and Nitrogen Through Neutron Transmutation Doping and Pre-Irradiation Chemical Vapor Deposition
This project aims to determine the temperature dependence of the extrinsic...
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NSUF 25-5238: Improved In-reactor Performance of SiC by n-Doping with Phosphorus and Nitrogen Through Neutron Transmutation Doping and Pre-Irradiation Chemical Vapor Deposition አሳይ -
NSUF 25-5240: Mechanical and microstructure properties of an optimized ODS alloy under neutron irradiation
A range of Fe-based alloys using various compositions and processing...
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NSUF 25-5240: Mechanical and microstructure properties of an optimized ODS alloy under neutron irradiation አሳይ -
NSUF 25-5241: Thermal Diffusivity Characterization of Irradiated Minor Actinide-Bearing Metal Fuel Pin G591 from the EBR-II X501 Experiment
Long-lived minor actinide (Am, Np) isotopes generated during nuclear reactor...
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NSUF 25-5241: Thermal Diffusivity Characterization of Irradiated Minor Actinide-Bearing Metal Fuel Pin G591 from the EBR-II X501 Experiment አሳይ -
NSUF 25-5246: Evaluating the Radiation Tolerance of ZrC under Extreme Irradiation Conditions
The project aims to study the radiation tolerance of ZrC under extreme...
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NSUF 25-5246: Evaluating the Radiation Tolerance of ZrC under Extreme Irradiation Conditions አሳይ -
NSUF 25-5247: Acoustoplasticity induced microstructural modification to mitigate stress corrosion cracking in stainless steel 316L
This work will study the irradiation assisted stress corrosion cracking...
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NSUF 25-5247: Acoustoplasticity induced microstructural modification to mitigate stress corrosion cracking in stainless steel 316L አሳይ -
NSUF 25-5253: Understanding Early Redistribution Dynamics in U-20Pu-10Zr Fuels Through EPMA
This project aims to elucidate the dynamics of restructuring and element...
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NSUF 25-5253: Understanding Early Redistribution Dynamics in U-20Pu-10Zr Fuels Through EPMA አሳይ -
NSUF 25-5264: Exploring radiation tolerance in novel FeCrVZrAl high entropy alloys for advanced fission reactor applications
This research project aims to investigate the effects of high-temperature ion...
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NSUF 25-5264: Exploring radiation tolerance in novel FeCrVZrAl high entropy alloys for advanced fission reactor applications አሳይ -
NSUF 25-5278: Radiation-induced segregation at coherent twin boundaries in 316L steels after low dose proton irradiation
The project objective is to irradiate two 316L austenitic steel samples with...
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NSUF 25-5278: Radiation-induced segregation at coherent twin boundaries in 316L steels after low dose proton irradiation አሳይ -
NSUF 25-5279: Characterization of Pellet-Cladding Interface Damage of Spent Nuclear Fuel during Fatigue Bending
A typical light water reactor (LWR) fuel pin is composed of enriched uranium...
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NSUF 25-5279: Characterization of Pellet-Cladding Interface Damage of Spent Nuclear Fuel during Fatigue Bending አሳይ