Conference Logo ProgramMaster Logo
Conference Tools for 2026 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools

About this Symposium

Meeting 2026 TMS Annual Meeting & Exhibition
Symposium Special Topics in Nuclear Materials: Reproducibility and Uncertainty; Hydrogen Effects; Space and Microreactor Systems
Sponsorship TMS Structural Materials Division
TMS: Nuclear Materials Committee
TMS: Advanced Characterization, Testing, and Simulation Committee
TMS: Mechanical Behavior of Materials Committee
Organizer(s) Stephen Taller, Oak Ridge National Laboratory
Charles A. Hirst, University of Wisconsin-Madison
Janelle P. Wharry, University of Illinois
Caleb Clement, Westinghouse Electric Company
Mary O'Brien, Los Alamos National Laboratory
Elizabeth Jane Kautz, North Carolina State University
Scope Nuclear materials research is continuously evolving within an environment of rapidly shifting socio-political, economic, and environmental policies and priorities, as well as in response to research advances across the broader materials science community. This symposium captures emergent topics to facilitate deep and timely discussions that will elevate the impact and visibility of these topics, and build research momentum in these areas. For TMS 2026, three emerging topics are identified:

Reproducibility and Uncertainty in Nuclear Materials Research:

The state-of-the-art for nuclear materials research is constantly progressing with improvements in experiment design, instrumentation, computational power, and analysis methods. As a result, there is a new ability to repeat or reproduce historical experiments and gain new understanding. Additionally modern methodologies likely reduce uncertainties in measurements from common alloys and materials. Presentations are sought that address the reproducibility and uncertainty of nuclear materials research studies with emphasis on new insights that can be gained from reproducing or reanalyzing historical studies. Both experimental and computational studies are encouraged.
Examples include:
• New insight gained from repeating historical experiments with modern methods and/or analyses
• Uncertainty in properties and radiation performance within an alloy specification (heat-to-heat variations)
• Uncertainty in experimental history (cycle length, reactor power, cycle ramp) and its propagation to scientific understanding
• Introduction of uncertainty through different length scales of examination (indentation size effect, SEM vs TEM particle quantification, etc)

Hydrogen Effects:
Small but mighty, hydrogen isotopes play a significant role in the performance of nuclear materials: from hydride embrittlement in zirconium alloys, to degradation of metal-hydride moderators in microreactors, to deuterium and tritium implantation in fusion plasma-facing materials. This mini-symposium seeks presentations on areas from experimental characterization to atomistic modeling of hydrogen-influenced phenomena in metallic and ceramic nuclear materials. Abstracts are invited, but are not limited to, those that investigate the following topics:
• Post-irradiation characterization of accelerator targets
• Hydride formation and mechanical properties impact in zirconium/structural alloys
• Fabrication, irradiation, and degradation of metal-hydrides
• Tritium interactions in liquid-facing and solid breeder materials
• Hydrogen isotope retention and release in fusion materials

Materials Challenges for Space and Microreactor Systems:

The space and defense sectors are increasingly turning to nuclear energy to power long-term space exploration, remote combat zones, and our increasingly militarized outer space. The nuclear thermal propulsion (NTP) and micro-reactor systems under consideration exhibit unique materials challenges. Their more compact designs require materials to operate at unprecedented thermal and irradiation fluxes, interface with coolants and/or propellants that are not well-understood, and withstand significant uptake of gases and transmutants including hydrogen. This mini-symposium invites abstracts investigating but not limited to:
• Novel materials and fuels for NTP or defense micro-reactors
• Irradiation-corrosion unique to space or micro-reactor environments
• Degradation phenomena in NTP or defense micro-reactor materials

Abstracts Due 07/29/2025
Proceedings Plan Planned:

PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE


Assessment of Hydrogen Diffusion in Vanadium for FLiBe Blanket Designs
Characterization of the Impact of Transmutation Gases on Deformation Mechanisms of Spallation Neutron Source Component Materials
Characterization of Zirconiumhydride Decomposition by Neutron Diffraction and Modeling
Degradation of Yttrium and Zirconium Hydrides Under Irradiation in the MIT Reactor
Deleterious Effect of Electrical Discharge Machining Interaction Layer on Metallic Zirconium Hydride Conversion Process
Density Functional Theory Analysis of Candidate Tritium Permeation Barriers for Vanadium Alloys as a Fusion Structural Material
Deuterium Retention in Grain Oriented, Additive Manufactured Tungsten
Effect of Electrolytic Hydrogen Charging on the Lattice Parameter of Copper Measured by Synchrotron HEXRD
Effect of Radiation Damage on Hydrogen Equilibrium Vapor Pressure over Irradiated Zircaloy-4
Effect of Sulfide Corrosion on the Interatomic Spacing of Copper Measured by Synchrotron HEXRD
Evaluating Measurement Consistency in Irradiated Stainless Steel Using Complementary Microscopy and Spectroscopy Techniques
Facing Technology Development Challenges for Space and Microreactor Systems
Fracture Behavior of ε-ZrH Assessed by Small Scale Mechanical Testing
Hydrogen Isotope Retention in Displacement Damaged Tungsten
Hydrogen Retention in Neutron-Irradiated Tungsten and Tungsten-Rhenium Alloys
Hydrogen Retention in Zirconium Hydride Moderator: Atomistic Insights Into the Role of Microstructural Defect Sinks
In-Situ TEM Study of Gamma Hydride Behavior During Thermal Cycling in Zircaloy-4: Transformation Kinetics, Mechanisms, and Sample Preparation Effects
Insights From Post-Irradiation Examination of Yttrium Hydride at ORNL and INL
Insights Into Radiation-Induced Ductility Enhancement of Inconel 718 Using In-Situ SEM-EBSD Tensile Testing
Irradiation Damaging EUROFER97 to High Dose at Different Temperatures
Irradiation Effects on Optical Fiber Sensors and Measurements
Mechanism of Helium-Assisted Hydrogen Retention in Ferritic-Martensitic Steels Under Irradiation
Molten Metallic Nuclear Fuel Containment: Challenges and Implications for Space Power and Propulsion
Neutron Irradiation Effects on Lithium Aluminate Pellets With Different Thickness
Phase Stability and Hydrogen Diffusion in Irradiated Yttrium Hydride
Post Irradiation Examination of an Irradiated 6061-T6 Aluminum Proton Beam Window
Quantifying and Reducing the Errors in Void Swelling Calculations of Irradiated Materials With Transmission Electron Microscopy
Replicating In-Service Hydriding of Zirconium Alloy Fuel Claddings Utilizing a Combined Experimental-Computational Approach
Revisiting He Bubble Measurements in Aged Pu Using Modern S/TEM Techniques
Sensitivities and Uncertainties in HFIR Materials Irradiation Experiments
Spatial Characterization of Hydrogen in Nuclear Materials
Thermal Gradient Effect on Defects Transport in Tungsten
Thermophysical Properties of Irradiated Yttrium Hydride Moderator Material
Time-Resolved Correlative Study of Hydride Phase Evolution in Zircaloy-4 Using In Situ XRD and EBSD-SEM
Toward Rapid Emulation of Neutron Damage With Ions: Helium Effects on Microstructural Evolution in Ion-Irradiated Historic Heats of V-4Cr-4Ti Alloy (US832665, US832864)
Understanding the Role of Hydrides in the Oxidation Behavior of Zircaloy-4
Using Thermo-Chemistry Modeling to Inform Metal Hydride and High Temperature Fuel Design, Operation, and Safety
X-Ray Absorption Signatures of Plutonium Alloys Accounting for Composition, Age, and Mechanical Stress


Questions about ProgramMaster? Contact programming@programmaster.org | TMS Privacy Policy | Accessibility Statement