Projects
-
NSUF 25-5165: Interplay of Nanoscale Heterogeneities and Radiation Damage in Compositionally Complex Alloys
Non-dilute multicomponent alloys, or compositionally complex alloys (CCAs),...
0 Datasetov
Zobraziť NSUF 25-5165: Interplay of Nanoscale Heterogeneities and Radiation Damage in Compositionally Complex Alloys -
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...
0 Datasetov
Zobraziť NSUF 25-5202: Atom probe tomography of HT-9 to evaluate the effect of neutron irradiation temperature, alloying element and heat treatment -
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...
0 Datasetov
Zobraziť NSUF 25-5206: Elucidating the Role of Polymeric Coatings in Optical Fiber Sensors under Neutron Irradiation -
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...
0 Datasetov
Zobraziť NSUF 25-5208: Investigating Ultraviolet Sensitive Avalanche Photodiodes by Ion Implantation in 4H-Silicon Carbide for High Temperature Sensing -
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...
0 Datasetov
Zobraziť NSUF 25-5218: Elevated temperature gamma irradiation of optical fibers sensors for spent nuclear fuel dry cask storage system canister structural health monitoring applications -
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...
0 Datasetov
Zobraziť NSUF 25-5224: High resolution characterization of U3Si2 fuel rodlets using Transmission Electron Microscopy and Atom Probe Tomography -
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...
0 Datasetov
Zobraziť NSUF 25-5225: Mechanical Properties Characterization and Atom Probe Tomography Preparation of BOR60 Neutron Irradiated T91 Steel Samples for Surrogate Ion-Irradiation Comparison -
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...
0 Datasetov
Zobraziť NSUF 25-5227: Assessing the Irradiation-Assisted Hydrothermal Degradation of Bulk GB Engineered SiC -
NSUF 25-5230: Determination of Swelling Across Temperatures in Vanadium Alloys Without Transmutation
Vanadium alloys were developed as candidate alloys for cladding materials of...
0 Datasetov
Zobraziť NSUF 25-5230: Determination of Swelling Across Temperatures in Vanadium Alloys Without Transmutation -
NSUF 25-5231: Effect of irradiation on 3D printed magnetostrictive materials
Magnetostrictive materials deform in response to a magnetic field and exhibit...
0 Datasetov
Zobraziť NSUF 25-5231: Effect of irradiation on 3D printed magnetostrictive materials -
NSUF 25-5237: Property measurement of LiF-NaF-ZrF4-UF4
For this RTE, the melting temperature of the salt will be measured using a...
0 Datasetov
Zobraziť NSUF 25-5237: Property measurement of LiF-NaF-ZrF4-UF4 -
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...
0 Datasetov
Zobraziť 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 -
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...
0 Datasetov
Zobraziť NSUF 25-5240: Mechanical and microstructure properties of an optimized ODS alloy under neutron irradiation -
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...
0 Datasetov
Zobraziť NSUF 25-5241: Thermal Diffusivity Characterization of Irradiated Minor Actinide-Bearing Metal Fuel Pin G591 from the EBR-II X501 Experiment -
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...
0 Datasetov
Zobraziť NSUF 25-5246: Evaluating the Radiation Tolerance of ZrC under Extreme Irradiation Conditions -
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...
0 Datasetov
Zobraziť NSUF 25-5247: Acoustoplasticity induced microstructural modification to mitigate stress corrosion cracking in stainless steel 316L -
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...
0 Datasetov
Zobraziť NSUF 25-5253: Understanding Early Redistribution Dynamics in U-20Pu-10Zr Fuels Through EPMA -
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...
0 Datasetov
Zobraziť NSUF 25-5264: Exploring radiation tolerance in novel FeCrVZrAl high entropy alloys for advanced fission reactor applications -
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...
0 Datasetov
Zobraziť NSUF 25-5278: Radiation-induced segregation at coherent twin boundaries in 316L steels after low dose proton irradiation -
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...
0 Datasetov
Zobraziť NSUF 25-5279: Characterization of Pellet-Cladding Interface Damage of Spent Nuclear Fuel during Fatigue Bending