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Meeting MS&T24: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments V
Presentation Title Advanced Characterization Capabilities of Nuclear Materials via NSUF
Author(s) Rongjie Song, Brenden J Heidrich
On-Site Speaker (Planned) Rongjie Song
Abstract Scope Advanced post-irradiation examination (PIE) techniques are required to design new or improve nuclear materials, characterize, understand in‑core behavior of fuel and materials, and support the qualification of new reactor materials. The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear science user facility. NSUF provides researchers access to PIE capabilities at Idaho National Laboratory and at a diverse mix of university, national laboratory and industrial partner institutions. The PIE capabilities include novel destructive and non-destructive techniques for radiation damage characterization, such as advanced diffraction techniques (X-ray, electron, or neutron) coupled to extreme environments; in-situ observation of microstructural evolution under irradiation; in-situ irradiation to monitor corrosive attack in coolant environments; in-situ irradiation and mechanical testing; and test methods for synergistic effects of superimposed extreme environments (temperature, irradiation, stress, corrosion) on materials behaviors. This talk will provide an overview of NSUF PIE capabilities.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced Characterization Capabilities of Nuclear Materials via NSUF
Advanced In-Situ Strain Mapping for Zr Oxidation by 4D-SPED
An In-Situ Transmission Electron Microscopy Study on the Synergistic Effects of Heating and Biasing of AlGaN/GaN High Electron Mobility Transistors
Atomic-Scale Hidden Point-Defect Complexes Induce Ultrahigh Irradiation Hardening in BCC Metals
Characterization of Aluminum Under Shock: Defects, Grain Orientation, and Phase Stability
Characterization of Radiation Damage in Nanocrystalline Ni- and Fe-Based Oxide Dispersion-Strengthened Alloys
Deciphering and Visualizing Helium Accumulation and Dynamics in Materials via In-Situ Characterization
Deployment and Testing of a Fiber-Based Instrument for In-Reactor Thermal Property Measurements at MIT Research Reactor
Determination of Molten Salt Thermal Conductivity Using Laser Flash Technique
Dynamics of Radiation Defect Accumulation in Non-Metallic Materials
Formation and Recover of Dislocations Under Deformation and/or Irradiation of Elemental Tantalum, a Step Toward Understanding Complex BCC Alloys.
Impact of Amorphous Pockets on Displacement Damage Evolution in Crystalline Silicon
Influence of Defects Length-Scale on Nuclear Graphite Properties
Interactions Between Radiation-Induced Defects and Shock in Al 1100
Investigation of Helium Bubble Formation at Tungsten-Dispersoid Interfaces in Dispersion-Strengthened Tungsten Alloys
L-1: Application of Laboratory-Based Photoelectron Spectroscopy with Hard and Soft X-Rays to Nuclear Forensics Characterization of Uranium Dioxide Fuel
L-2: Effect of Swift Heavy Ion Irradiation on Silicon Carbide
Localized Crystallization of Zr Following Heavy Ion Irradiation of HfNbTaZr MPEA
Machine Learning and Molecular Dynamics-Coupled X-Ray Absorption Spectroscopy for Disordered Multicomponent Systems
Microstructural and Chemical Evolution Studies of U-10Zr Metallic Fuel and HT9 Cladding from Fast Flux Test Facility
Microstructural Evolution in 316L Stainless Steel Under Lead-Bismuth Eutectic Corrosion
Nanoscale Redistribution of Lithium in Neutron Irradiated LiAlO2
Neutron-Induced Reversible Nanostructuring of GeSe2
Quantitative Phase Characterization of Nuclear Cements and Concretes Using Non-Destructive 3D Automated Mineralogy and Enhanced Deep-Learning Reconstruction via X-ray Microscopy
Real-time Neutron Diffraction to Support Interpretation of DSC Results on Zr-2.5Nb for Reactor Pressure Tubes
Strong Dependence of 2D Material Radiation Tolerance on the Composition of the 2D Material and Its Surrounding Environment
Structural Characterization of Ultra-High Temperature Ceramics in Three Dimensions for Statistical and Physics-Based Modeling
Superimposed Effects of Texture and Grain Shape Anisotropy on Biaxial Creep Behavior of Nb-Modified Zircaloy-4 Cladding
Synthesis and Irradiation of Uranium Carbide and Nitride for TRISO Development
Thermophysical Characterisation of Zirconium-Based Nuclear Materials
Tungsten-Based WTaVCr Refractory High Entropy Alloys for Fusion Energy Applications
Understanding Irradiation Assisted Hydrogen Embrittlement Using In Situ Coherent X-Ray Imaging
Understanding the Mechanism of Fission Gas Re-Solution and Blistering in UMo Fuel via Atomistic Modelling
Understanding the Surface and Near Surface via Nanomechanical Mapping

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