Projects
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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 25-5279: 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 25-5285: Probing the Effects of Temperature, Radiation, and Fuel Cladding Chemical Interaction on Irradiated HT-9 Cladding via In-Situ Micro-Tensile Testing
Current HT-9 creep and deformation models in the BISON framework consistently...
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NSUF 25-5295: High-Temperature In-Situ Micro-Tensile Testing of FFTF-Irradiated HT9 Cladding from U-10Zr Fuel Pins
Current HT-9 creep and deformation models within the BISON framework...
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NSUF 25-5296: Inter-Phase Localized Fracture: A New Mechanism for RPV Embrittlement
The objective of this project is to understand inter-phase localized...
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NSUF 25-5303: Influence of Carbon Stoichiometry and Microstructure on the Irradiation Performance of Uranium Carbide Fuels
Uranium carbide (UC) is a candidate fuel for advanced reactors due to its...
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NSUF 25-5313: Investigation of Elastic Interactions and Mechanical Behaviors in NF709 Using Coherence Enhanced High Energy Diffraction Microscopy
Irradiation introduces various defects into the lattice, which interact with...
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NSUF 25-5315: Investigating helium and hydrogen behavior in beryllium carbide at high temperature using in-situ ion irradiations
Graphite, a candidate moderator for advanced reactors, exhibits several...
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NSUF 25-5316: In-situ dual beam irradiation of BCC-L21 and BCC-B2 alloys for void formation
Compositionally complex refractory superalloys are an area of significant...
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NSUF 25-5317: In situ TEM study of irradiation resistance of C-SiC/ZrC composites
Methods: This proposal is to use the IVEM - Tandem Facility to conduct an in...
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NSUF 25-5326: Linking Subgrain Lattice Strain to Irradiation Defect Evolution in Additively Manufactured 316H Stainless Steel
Fusion-based additive manufacturing (AM), commonly referred to as 3D...
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NSUF 25-5332: Neutron Irradiation Damage and Transmutation Products in Diffusion-Bonded 316L SS/B4C
Shielding mass remains one of the most critical constraints in nuclear...
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NSUF 25-5338: Investigation of Fission Product Speciation in UN MiniFuel Particles
This work aims to characterize fission product speciation in irradiated UN...
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NSUF 25-5356: Effect of ion irradiation and dose rates on 316L oxide-dispersion-strengthened steel additively manufactured by wire-powder laser-directed energy deposition
The oxide dispersion strengthened (ODS) alloys have emerged as promising...
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NSUF 25-5368: Free Field Characterization of the Neutron RADiography Reactor Dry Tube with Demonstration of Novel Epithermal Dosimetry Materials
Non-LWR designs often rely on fission caused by neutrons in the epithermal...
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NSUF 25-5377: Individual and Synergistic Effects of Solutes on Precipitate Phase Selection in Neutron Irradiated RPV Model Alloys
The structural integrity of reactor pressure vessels (RPVs) is critical to...
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NSUF 25-5378: Isotopic Analysis of AGN-201 Fuel to Support Benchmarking Project
The objective of this RTE is to conduct ICP-MS (Inductively Coupled Plasma -...
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NSUF 25-5379: Spatial Mapping of Irradiated Metal Hydrides Using Combined X-ray Tomography and Diffraction
Metal hydrides are promising moderators for use with small modular rectors,...
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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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View NSUF 25-5381: Investigating the out-of-plane IASCC propagation in neutron-irradiated 316L stainless steel made by laser powder bed fusion -
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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