Projects
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NSUF 24-5018: Neutron/Proton Round Robin: What role does irradiation type play in enhancing ordering in Ni-Cr-based alloys?
'It has been shown that irradiation can enhance ordering in selected Ni-Cr...
0 Datasetov
Zobraziť NSUF 24-5018: Neutron/Proton Round Robin: What role does irradiation type play in enhancing ordering in Ni-Cr-based alloys? -
NSUF 24-5019: Nondestructive Evaluation of Fracture Properties in Irradiated Light Water Reactor Pressure Vessel Steels
The proposed research will utilize sets of utility owned irradiated RPV...
0 Datasetov
Zobraziť NSUF 24-5019: Nondestructive Evaluation of Fracture Properties in Irradiated Light Water Reactor Pressure Vessel Steels -
NSUF 24-5020: Elemental effects on radiation damage in tempered martensitic steels neutron irradiated to high doses at fast reactor relevant temperatures
Embrittlement of tempered martensitic (TM) steels is a key issue for their...
0 Datasetov
Zobraziť NSUF 24-5020: Elemental effects on radiation damage in tempered martensitic steels neutron irradiated to high doses at fast reactor relevant temperatures -
NSUF 24-5021: Radiation Effects of High Entropy Alloys
The project's objective is to gain a comprehensive understanding of neutron...
0 Datasetov
Zobraziť NSUF 24-5021: Radiation Effects of High Entropy Alloys -
NSUF 24-5022: Advanced hydride moderator irradiations for microreactor and space nuclear reactor deployment
With the recent signing of Space Policy Directive-6, a US policy goal for...
0 Datasetov
Zobraziť NSUF 24-5022: Advanced hydride moderator irradiations for microreactor and space nuclear reactor deployment -
NSUF 24-5023: Characterization of Irradiation-Assisted Stress Corrosion Cracking in 316 Stainless Steel Baffle-Former Bolts Harvested from Commercial Pressurized Water Reactor
The objective of this project is to assess the mechanisms for initiation and...
0 Datasetov
Zobraziť NSUF 24-5023: Characterization of Irradiation-Assisted Stress Corrosion Cracking in 316 Stainless Steel Baffle-Former Bolts Harvested from Commercial Pressurized Water Reactor -
NSUF 24-5024: Measurement of Time-Dependent Transmissivity of Materials for Optical Sensors and Instrumentation
Optical sensors critically depend on the passage of light through transparent...
0 Datasetov
Zobraziť NSUF 24-5024: Measurement of Time-Dependent Transmissivity of Materials for Optical Sensors and Instrumentation -
NSUF 24-5033: Deciphering the role of nitrogen on the performance of ferritic-martensitic steels under high-dose irradiation using N-15 isotope doping
This project aims to investigate the role of nitrogen (N) in suppressing void...
0 Datasetov
Zobraziť NSUF 24-5033: Deciphering the role of nitrogen on the performance of ferritic-martensitic steels under high-dose irradiation using N-15 isotope doping -
NSUF 24-5050: Mechanical Assessment of Pd Corroded Surrogate and Irradiated TRISO Particles
Pd, a high yield fission product, has been shown to migrate and cluster...
0 Datasetov
Zobraziť NSUF 24-5050: Mechanical Assessment of Pd Corroded Surrogate and Irradiated TRISO Particles -
NSUF 24-5069: Influence of laser welding on deformation mechanisms in irradiated and weld-repaired Ni-Cr alloys
The objective of this project is to evaluate the influence of laser welding...
0 Datasetov
Zobraziť NSUF 24-5069: Influence of laser welding on deformation mechanisms in irradiated and weld-repaired Ni-Cr alloys -
NSUF 24-5070: Neutron Irradiation and PIE of ZrC Coated Surrogate Particle Fuel in IN-Pile Steadystate Extreme Temperature (INSET) Testbed
Tristructural isotropic (TRISO) and other coated particle fuels have been...
0 Datasetov
Zobraziť NSUF 24-5070: Neutron Irradiation and PIE of ZrC Coated Surrogate Particle Fuel in IN-Pile Steadystate Extreme Temperature (INSET) Testbed -
NSUF 24-5077: In-Operando Performance Characterization of On-Chip Integrated SiC Pressure/Temperature Sensors under Irradiation
NASA and DOE are developing a 40-kW Lunar Fission Surface Power Technology...
0 Datasetov
Zobraziť NSUF 24-5077: In-Operando Performance Characterization of On-Chip Integrated SiC Pressure/Temperature Sensors under Irradiation -
NSUF 24-5078: In-situ TEM Heating Investigation of M23C6 Stability in Neutron Irradiated HT9
HT9 is the leading structure materials for various advanced reactor systems...
0 Datasetov
Zobraziť NSUF 24-5078: In-situ TEM Heating Investigation of M23C6 Stability in Neutron Irradiated HT9 -
NSUF 24-5080: Accelerated evaluation of friction stir welding for on-site repairs using HFIR irradiation, welding, accelerator irradiation, and characterization
Friction stir welding (FSW) is a cutting-edge technique enabling potential...
0 Datasetov
Zobraziť NSUF 24-5080: Accelerated evaluation of friction stir welding for on-site repairs using HFIR irradiation, welding, accelerator irradiation, and characterization -
NSUF 24-5081: Understanding the effect of Helium and neutron irradiation in ODS alloys.
This proposal leverages previously irradiated ODS materials (14YWT) from the...
0 Datasetov
Zobraziť NSUF 24-5081: Understanding the effect of Helium and neutron irradiation in ODS alloys. -
NSUF 24-5082: Interactions between Neutron Irradiation and Oxide Based Inclusions in Additively Manufactured Austenitic Stainless Steels
Additive manufacturing (AM) provides an innovative process route for...
0 Datasetov
Zobraziť NSUF 24-5082: Interactions between Neutron Irradiation and Oxide Based Inclusions in Additively Manufactured Austenitic Stainless Steels -
NSUF 24-5092: Advanced microstructure characterization of irradiation impact on corrosion performance of SiC-SiC composite materials
The PI has access to 6 irradiated samples obtained from SiC-SiC composites...
0 Datasetov
Zobraziť NSUF 24-5092: Advanced microstructure characterization of irradiation impact on corrosion performance of SiC-SiC composite materials -
NSUF 24-5097: Characterization of U8Pu10Zr fluff sample
This proposal aims to investigate the axial swelling behavior of metallic...
0 Datasetov
Zobraziť NSUF 24-5097: Characterization of U8Pu10Zr fluff sample -
NSUF 24-5108: Microstructural Characterization of Pressurized Water Reactor Harvested Core Barrel Weld Materials
The objective of this work would be to perform detailed microstructural...
0 Datasetov
Zobraziť NSUF 24-5108: Microstructural Characterization of Pressurized Water Reactor Harvested Core Barrel Weld Materials -
NSUF 24-5113: Investigating ion irradiation at high temperatures on high entropy carbide ceramics using correlative positron annihilation spectroscopy and transmission electron microscopy
High entropy carbides (HECs) are an emerging class of ultra-high temperature...
0 Datasetov
Zobraziť NSUF 24-5113: Investigating ion irradiation at high temperatures on high entropy carbide ceramics using correlative positron annihilation spectroscopy and transmission electron microscopy