| PI Name | Institution | Project Title |
| Osman El Atwani | Pacific Northwest National Laboratory | Exploring radiation tolerance in novel FeCrVZrAl high entropy alloys for advanced fission reactor applications |
| Pascal Bellon | University of Illinois at Urbana-Champaign | Radiation-induced segregation at coherent twin boundaries in 316L steels after low dose proton irradiation |
| Lei (Raymond) Cao | The Ohio State University | Investigating Ultraviolet Sensitive Avalanche Photodiodes by Ion Implantation in 4H-Silicon Carbide for High Temperature Sensing |
| Sunil Chakrapani | Michigan State University | Acoustoplasticity induced microstructural modification to mitigate stress corrosion cracking in stainless steel 316L |
| Zhangxian Deng | Boise State University | Effect of irradiation on 3D printed magnetostrictive materials |
| Nicholas Fassino | Oklo Inc. | Thermal Diffusivity Characterization of Irradiated Minor Actinide-Bearing Metal Fuel Pin G591 from the EBR-II X501 Experiment |
| Elizabeth Getto | United States Naval Academy | Mechanical and microstructure properties of an optimized ODS alloy under neutron irradiation |
| Hannah Jones | University of Oxford | Mechanical Properties Characterization and Atom Probe Tomography Preparation of BOR60 Neutron Irradiated T91 Steel Samples for Surrogate Ion-Irradiation Comparison |
| Toni Karlsson | Idaho National Laboratory | Property measurement of LiF-NaF-ZrF4-UF4 |
| Rory Kennedy | Idaho National Laboratory | Improved In-reactor Performance of SiC by n-Doping with Phosphorus and Nitrogen Through Neutron Transmutation Doping and Pre-Irradiation Chemical Vapor Deposition |
| Seungsu Kim | Texas A&M University | Evaluating the Radiation Tolerance of ZrC under Extreme Irradiation Conditions |
| Konstantina Lambrinou | University of Huddersfield | Assessing the Irradiation-Assisted Hydrothermal Degradation of Bulk GB Engineered SiC |
| Elliot Marrero | University of Illinois at Urbana-Champaign | Inter-Phase Localized Fracture: A New Mechanism for RPV Embrittlement |
| Bao-Phong Nguyen | University of Florida | Probing the Effects of Temperature, Radiation, and Fuel Cladding Chemical Interaction on Irradiated HT-9 Cladding via In-Situ Micro-Tensile Testing |
| Paul Ohodnicki | University of Pittsburgh | Elevated temperature gamma irradiation of optical fibers sensors for spent nuclear fuel dry cask storage system canister structural health monitoring applications |
| Ramprashad Prabhakaran | Pacific Northwest National Laboratory | Atom probe tomography of HT-9 to evaluate the effect of neutron irradiation temperature, alloying element and heat treatment |
| Allison Probert | University of Florida | Understanding Early Redistribution Dynamics in U-20Pu-10Zr Fuels Through EPMA |
| Yadukrishnan Sasikumar | Oak Ridge National Laboratory | Characterization of Pellet-Cladding Interface Damage of Spent Nuclear Fuel during Fatigue Bending |
| Federico Scurti | Pennsylvania State University | Elucidating the Role of Polymeric Coatings in Optical Fiber Sensors under Neutron Irradiation |
| Sohail Shah | Idaho National Laboratory | High resolution characterization of U3Si2 fuel rodlets using Transmission Electron Microscopy and Atom Probe Tomography |
| Mitra Taheri | Johns Hopkins University | Interplay of Nanoscale Heterogeneities and Radiation Damage in Compositionally Complex Alloys |
| Matthew Weinstein | TerraPower | Determination of Swelling Across Temperatures in Vanadium Alloys Without Transmutation |
| Guang Yang | Idaho National Laboratory | High-Temperature In-Situ Micro-Tensile Testing of FFTF-Irradiated HT9 Cladding from U-10Zr Fuel Pins |
