Projects
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NSUF 25-5381: Investigating the out-of-plane IASCC propagation in neutron-irradiated 316L stainless steel made by laser powder bed fusion
The first-of-its-kind irradiation-assisted stress corrosion crack (IASCC)...
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NSUF 25-5388: Evaluating Irradiation-Induced Degradation of Phase Boundary Strength in Cast Stainless Steels
This project addresses a critical knowledge gap in predicting fracture...
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NSUF 25-5391: Microstructural characterization of U-10wt.%Zr specimens from MFF-2 experiment for FAST experiment benchmarking
Uranium-zirconium fuels have achieved high burn-up performance up to 19 at.%...
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NSUF 25-5392: In Situ Characterization of Irradiation-Induced Swelling in 316L Steel Foils Using High Temperature Rutherford Backscattering Spectroscopy
This project aims to develop a novel in situ characterization technique for...
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NSUF 25-5398: Quantifying Recovery and Recrystallization Kinetics of Irradiated Zircaloy-4 Cladding During Time-at-Temperature Transients
To meet growing energy demands, the existing nuclear reactor fleet must...
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NSUF 25-5402: Microstructural characterization of structural alloys under combined proton-irradiation and molten salt corrosion
Molten salt reactors (MSRs) are promising advanced reactor designs due to...
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NSUF 25-5405: Investigation of Anomalously High Ionization Produced by 254 eV Nuclear Recoils in Germanium
Detailed characterization of detector response to nuclear recoils is crucial...
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NSUF 25-5409: In-Situ Synchrotron X-ray Diffraction Study During Tensile Deformation of Neutron Irradiated MA957 ODS Alloy
This research explores the hypothesis that neutron irradiation alters the...
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NSUF 25-5412: Impact of irradiation induced defects on thermal conductivity of zirconia
This project aims to quantify how radiation-induced defects affect thermal...
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NSUF 25-5414: Real-time TEM observation of cavity evolution with helium implantation and nanomechanical loading in Fe and Ni based alloys
Fe-Cr based ferritic steels and nickel alloys are used extensively in nuclear...
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NSUF 25-5420: Radiation induced changes in oxide particles in 14YWT alloys produced from gas atomization reaction synthesis powders
Ferritic oxide dispersion strengthened (ODS) alloys are one of the most...
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NSUF 25-5423: Radial Uranium Isotopic Analysis of Irradiated U-19Pu-10Zr Fuel Using FIB-ToF-SIMS
The objective of this work is to characterize uranium isotopics as a function...
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NSUF 25-5434: Examining Mechanical Performance of Alloy T91 To High DPA using Nanoindentation
We propose to characterize the changes in mechanical properties in T91...
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NSUF 25-5446: Irradiation Effects on Nanolayered Nuclear Fuels
Metallic nuclear fuels offer significant advantages over commonly used...
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NSUF 25-5453: Irradiation to enhance NZFMR signal by increasing defects
This project aims to investigate the effect of controlled ion irradiation on...
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NSUF 25-5468: X-ray diffraction and eddy current study of irradiation growth in zirconium alloys
We propose to perform Frequency Scanning Eddy Current Eddy Current and...
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NSUF 25-5476: Evaluation of Microstructural Integrity of ATR-Irradiated Yttrium Hydride (YHₓ)
This project aims to evaluate the microstructural integrity of ATR(Advanced...
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NSUF 25-5486: Ceramic Matrix Composite Post Irradiation Examination
High-temperature, post-irradiated properties will be measured for two-...
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NSUF 25-5487: Evaluating the role of FeCrAl Alloy as a Hydrogen Permeation Barrier in Irradiated Yttrium Hydrides through In-Situ Synchrotron X-Ray Diffraction Studies
Factory-fabricated and truck-transportable nuclear microreactors rely on...
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View NSUF 25-5487: Evaluating the role of FeCrAl Alloy as a Hydrogen Permeation Barrier in Irradiated Yttrium Hydrides through In-Situ Synchrotron X-Ray Diffraction Studies -
NSUF 25-5507: Mechanistic Pathways of Fuel–Cladding Chemical Interactions via Ion Irradiation of Diffusion Couples
The development and qualification of advanced nuclear fuels are shifting from...
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