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Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Accelerated Qualification Methods for Nuclear Reactor Structural Materials
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On-Site Speaker (Planned)
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Keywords Nuclear Materials, Mechanical Properties,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Accelerated Creep Evaluation of L-PBF 316H Stainless Steel Using High-Temperature Nanoindentation
Accelerated Qualification of Structural Materials by High Throughput Mechanical Characterization
Accelerated Screening of the Radiation Tolerance of MPEAs for Nuclear Applications
Advancing the Understanding of Mechanical Properties of Diffusion-Bonded 316H and Alloy 617 for High-Temperature Applications
Beam-On Characterization of Nuclear Structural and Functional Materials
Building a Cohesive ML Ecosystem for Accelerated Nuclear Materials Qualification
Closing the Gap Between Neutron and Ion Irradiations
Computationally Accelerated Design of Multi-Principle-Element Alloys for Plasma Facing Components
Coupled Evolution of Spinodal Decomposition and Grain Boundary Radiation-Induced Segregation in Model Austenitic Alloys
Dependence of Grain Boundary Structure on Radiation Induced Segregation and Tritium Distribution in Coated 316 Stainless Steel Cladding
Down-Selecting Nb-Free Cu Alloys for Fusion Applications Using In Situ Transient Grating Spectroscopy
Effect of Shock Deformation on Hardening Due to Self-Ion Irradiation in Stainless Steel 316L
Effect of Side Groove and Temperature on the Fracture Behavior of Small HT9 Steel Specimens
Estimating High-Temperature Mechanical Properties from Micro-Indentation of Proton-Irradiated Stainless Steels
Extraction of Mechanical Property Information from Ion Irradiated LPBF 316 Steels
Fatigue Testing of Miniature Alloy 709 Specimens
High-Temperature Creep Properties of Solution Annealed, Additively Manufactured 316H Stainless Steel: Effects of Process Parameter and Build Direction
High-Throughput Dual-Ion Beam Irradiation and Autonomous Synthesis Platform for Accelerated Nuclear Materials Design for Fusion Applications
High-Throughput Methods for Analyzing Radiation Induced Swelling in Nuclear Structural Materials
High-Throughput Synthesis and Characterization of Refractory High Entropy Alloys for Fusion Applications
In-Situ Loading and Corrosion of Cr Coated ZIRLO with Scratch Defects
In-Situ Precession-Assisted Four-Dimensional Scanning Transmission Electron Microscopy (4D-STEM) Study of Initial Zr Oxidation Under Water Vapor and Oxygen
Investigating the Mechanisms Driving Irradiation Induced Grain Subdivision
Irradiation Effects on Microstructure and Mechanical Properties of Oxide Dispersion Strengthened Steel MA956
K-1: Pushing the Limits of Backscatter Electron Imaging of Radiation-induced Voids
K-2: Standardising Reactor Pressure Vessel Steel Irradiation Data to Overcome Archiving and Mining Challenges
K-3: Understanding the Effect of Nitrogen on Cavity Formation and Precipitate Stability Using Correlative STEM-APT Technique
Long-term Thermal Aging Behavior and Strength Reduction in a Laser Powder Bed Fusion 316H Stainless Steel
Machine Learning-Based Correlation of Charpy Impact Properties for Sub and Standard Sized Specimens
Material-Based Time-At-Temperature (t@T) Criterion to Support Licensing Strategies Post-Critical Heat Flux
Mechanical Response of Bimetallic Inconel 625 and Stainless Steel 316 Fabricated Via Selective Powder Deposition
Mechanisms-Based Creep-Fatigue Analysis of Alloy 617 for Advanced High-Temperature Nuclear Applications
Phase Interactions Affect Local Mechanical Response in RPV Steels
Quantification of Radiation-Induced Nanoprecipitate Dissolution Mechanisms in Fe-Based Binary Alloys
Radiation Induced Segregation in Metallic Alloys: Insights from Phase Field Modeling
Radiation Response of Wrought and Additively Manufactured Alloy 709 Under Dual Ion Irradiation at Reactor-Relevant Conditions
Simulating Fission Neutron Irradiated Tungsten with Self-Ion Irradiation for Predicting Damage in Commercial Nuclear Fusion Reactors
Spark Plasma Sintering of Dispersion Strengthened Tungsten Alloys for Fusion
Strain Field and Chemical Evolution of MX Precipitates in Model Ferritic Alloys After Neutron Irradiation at 490°C to 7.4 Dpa
The Ion Irradiation Response and Precipitate Stability of V-4Cr-4Ti Alloys for Fusion Structural Applications
Understanding Corrosion Mechanisms of Structural Alloys in Light Water Reactor Environments: An In-Situ X-Ray Diffraction Imaging Study
Understanding Radiation Effects in Friction Stir and Laser Welds in MA956 Under Ion Irradiation
Use of Small Angle Neutron Scattering to Characterize Radiation Effects and Thermal Response
Using Digital Image Correlation to Accelerate Understanding of Fuel Cladding Performance Under Accident Scenarios
Using Stress Relaxation Testing to Accelerate the Evaluation of the Long-Term Creep Performance of Alloy GRX-810
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