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About this Symposium

Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Interrelated Extremes in Materials Degradation for Fission and Fusion Environments
Sponsorship TMS Structural Materials Division
TMS: Nuclear Materials Committee
TMS: Corrosion and Environmental Effects Committee
Organizer(s) Jianqi Xi, University of Illinois Urbana-Champaign
Bai Cui, University of Nebraska-Lincoln
Janelle P. Wharry, University of Illinois
Haozheng Qu, GE Global Research
Samuel A. Humphry-Baker, Imperial College London
Dalong Zhang, Baylor University
Scope The fast-growing energy demand and the need to limit greenhouse gas emissions have led to the acknowledgment of the importance of increasing nuclear energy efficiency. This necessitates the development of nuclear materials that can withstand increasingly extreme environments. Advances in both fission and fusion reactors create exceptionally harsh working conditions for materials, requiring them to operate at higher temperatures and endure more intensive radiation doses while maintaining integrity in chemically aggressive environments. In some cases, these environmental effects can even couple with each other, further degrading material performance, and thus requiring fundamental improvements. However, improving materials for nuclear applications is a daunting challenge, especially in the absence of a comprehensive understanding of material behavior in complex and highly coupled extreme environments. Various approaches are employed to explore materials degradation, including the integration of in-situ experimental characterization, multiscale modeling, and machine learning prediction, etc. These methods open new avenues for better understanding the interplay of coupled extremes in materials degradation within nuclear fission and fusion environments. This symposium seeks to explore the impact of interrelated extremes on materials degradation in nuclear environments, providing a platform for discussing emerging insights, experimental observations, and theoretical advancements. By bringing together researchers from diverse disciplines, this symposium will enhance our collective understanding of coupled degradation mechanisms and inform the development of more resilient nuclear materials.

Abstracts are solicited in, but not limited to, the following areas:
· Coupling of radiation and mechanical stress effects on materials degradation.
· Interplaying of radiation and corrosion effects on materials degradation.
· Effects corrosion and mechanical stress on materials response.
· Combined effects of radiation, corrosion, and mechanical stress on materials degradation.
· Novel methods development in tackling coupled extremes environment.
· Experimental, modeling, and combined experimental-modeling studies are of interest.

Abstracts Due 07/29/2025
Proceedings Plan Planned:

PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE


Accelerating Nuclear Materials Development Through Thermal Gradient Ion Irradiations
Analysis of Attenuation Data From the Beltline of the Reactor Pressure Vessel From the Decommissioned ZION 1 Nuclear Power Plant
Assessment of Brittle Fracture of 304L Austenitic Stainless Steel – Material of Light Water Reactor Core Internals
Design Kinetic Parameters for Improved Resilience of Materials Under Irradiation
Detailed Post-Irradiation Examination of Harvested PWR Baffle-Former Bolts
Developing Dispersion-Strengthened Tungsten to Withstand Coupled Extremes in Fusion Reactors
Development of In-Situ Irradiation Creep Testing and Application to a Ferritic-Martensitic Steel
Dislocation Effects on High Temperature He Embrittlement in Iron-Based Alloys
Disordering and Defect Evolution Processes at Epitaxial Fe3O4 / Cr2O3 and Fe2O3 / Cr2O3 Interfaces Under Irradiation
Evaluation of SiC-Based Composite Tubes Under Multi-Physics Environments for Accident-Tolerant Cladding Development
Ghosts in the Mechanism: Corrosion Happening at the Same Time as Other Stuff
He Ion Irradiation Induced Defect Evolution and Micromechanical Response of W
High-Throughput Synchrotron Methods for Fusion Materials Research
Impact of Oxidation Temperatures and Different Helium Irradiation Doses-Induced Defects in Fe-18Cr
Integrated Model of Grain Growth in Tungsten Armor Materials Under ARC Plasma Edge Operation Conditions
Interphase Characterisation and Testing on SiC-Based CMCs for Fusion Applications
Investigating the Effect of High-Temperature Ion Irradiation on the Microstructures and Mechanical Properties of (Cr,Hf,Ta,Ti,Zr)C and (Hf,Ta,Ti,W,Zr)C Compositionally Complex Carbides
Investigation of Neutron Irradiation Effects on T91 Ferritic/Martensitic Steel for Fusion Reactor Applications
Irradiation Temperature and Mechanical Properties in Neutron Irradiated Ferritic Steel
Predicting Fracture Toughness Degradation in Irradiated Duplex Structure Stainless Steels Using Data-Driven Methods
Review of Point Defect Structures in Hexagonal Close Packed Metals and Across the Periodic Table
Simulated Ex-Service SFR Fuel Cladding for Characterization of Degradation Under DGR Groundwater Conditions
Simultaneous Irradiation and Corrosion in High Temperature Coolants - The Plot Thickens
Study on Corrosion Properties of F82H/SUS316L Dissimilar Joints Produced by Fiber Laser Welding or Friction Stir Welding
Three Dimensional Characterization of the Microstructures of PWR Baffle Former Bolts After 40 Years in Service
Transmission Electron Microscopy of Second Phase Precipitates in Zirconium Alloys Exposed to Neutron Irradiation in the Advanced Test Reactor
Understanding Coupled Environments Radiation +
Understanding Synergistic Degradation Mechanisms in Nuclear Materials Through Coupled Environment Testing
Vessel Material Selection and Design for the ARC Fusion Power Plant


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