ProgramMaster Logo
Conference Tools for 2022 TMS Annual Meeting & Exhibition
Register as a New User
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Symposium
Meeting 2022 TMS Annual Meeting & Exhibition
Symposium Synergistic Irradiation, Corrosion, and Microstructural Evolution in Nuclear Materials
Sponsorship TMS Structural Materials Division
TMS: Nuclear Materials Committee
Organizer(s) Djamel Kaoumi, North Carolina State University
Michael Philip Short, Massachusetts Institute of Technology
Peter Hosemann, University of California, Berkeley
Stephen Raiman, Texas A&M University
Raluca Scarlat, University of California, Berkeley
Aaron Kohnert, Los Alamos National Laboratory
Ryan Michael Schoell, North Carolina State University
Philip Edmondson, Oak Ridge National Laboratory
Celine Cabet, Commissariat a l'Energie Atomique
Scope All materials in nuclear reactor cores are simultaneously exposed to ionizing radiation and a corrosive environment: pressurized hot water in LWRs, molten salt in MSRs and liquid salt immersion blanket fusion reactors, liquid metal in LMFRs, etc. Both corrosion and irradiation can produce significant microstructural changes leading to degradation of material properties. These two phenomena are usually studied through a separate effect approach, which can be scientifically useful but practically limited since corrosion and irradiation happen simultaneously in the reactor, not without synergy. Unfortunately, the coupled effects of irradiation and corrosion are not well understood, nor even well characterized. While irradiation can enhance/accelerate corrosion in some environments, it has be found to decelerate it in others. In any case, while corrosion can have different manifestations depending on the material and the corrosive medium, its kinetics and mechanisms can be affected by concomitant irradiation induced defects. Such coupled effects of irradiation and corrosion which are the focus of the Energy Frontiers Research Center FUTURE (Fundamental Understanding of Transport Under Reactor Extremes) are thus of special interest to this symposium.

In this symposium, we wish to assemble and highlight the relatively new and rapidly growing field of simultaneous irradiation and corrosion in nuclear materials. Similarities between corrosion mechanisms and how they are affected by radiation are expected to evolve, thus bringing together the experts in this field is expected to solicit scientific similarities and delineate descriptive differences between materials coupled with environmental degradation during irradiation.

Specific topics where contributions are encouraged include:
- Studies leading to a better understanding of corrosion mechanisms without irradiation in real or simulated nuclear environments (pressurized hot water, molten salt, liquid metal)
- Corrosion and oxidation of irradiated materials in similar environments
- Radiation damage in ceramic oxides to better understand the nature of defects in oxides, including modelling studies that help understand the properties of irradiation induced defects in oxides
- Finally, serial and simultaneous irradiation/corrosion studies enabling a better understanding of the synergy of irradiation and corrosion processes regardless of the corrosive medium

For all topics, in situ characterization and measurement techniques which probe the kinetics/mechanisms of corrosion coupled with irradiation, either in parallel or in series, are particularly welcome. Both experimental and theoretical/computational studies are solicited with particular emphasis on linking state-of-the-art modeling with experimental observations.

Abstracts Due 07/19/2021
Proceedings Plan Planned:

4D-STEM and Atomic Resolution Analysis of He–rich Gas Bubbles Formed in Au Thin Films via He-ion Irradiation
Atomic Level Mechanisms Underlying Hydrothermal Corrosion of Silicon Carbide in Nuclear Reactors
Characterizing Commercial Alloys Undergoing Simultaneous Molten Salt Corrosion and Proton Irradiation
Cooperative Role of Pressure- and Corrosion on Stress Buildup of the High Temperature LWR Pipes
Decoupling of Ion Irradiation Effects on the Corrosion Rate of Zirconium Alloys: Experiment and Modelling
Defects and Disorder in Swift Heavy Ion-irradiated, Fluorite-derived Complex Oxides
Development of Coatings to Provide Corrosion Resistance and Tritium Retention for Application in Nuclear Fusion Reactors
Dramatic E-beam Enhancement of Zircalloy-4 Corrosion
Effect of Ion Irradiated Microstructure on Molten Salt Corrosion of Hastelloy N
Effect of Ion Irradiation on the Corrosion of 304SS in PWR Simulated Water Chemistry
Effect of Phosphorus (P) on Precipitation and Segregation Behavior in Neutron Irradiated Reactor Pressure Vessel Steels
Effects of Pre-irradiation on the Corrosion Behavior of I600 in Hydrogenated Water
Effects of Water Radiolysis and Displacement Damage during Simultaneous Irradiation and Corrosion of 316L Stainless Steel
Electrochemical Behavior of Fuel Cladding under In-situ UV Irradiation
Heavy-ion Irradiation Induced Cation Intermixing in Lanthanide Pyrochlores
In-situ Grain Growth of Nanocrystalline UO2
In-situ Measurement and Analysis of Structural Alloy Corrosion in Liquid Metals
In situ Monitoring of Corrosion Progression under Irradiation in the Irradiation-Corrosion Experiment (ICE)
In Situ Observations of the Amorphization Behavior of Fe2O3, Cr2O3, and Al2O3 under Ion Irradiation
Influence of Hydrogen and Irradiation on Transition Reference Temperature of Low-alloy Reactor Pressure Vessel Steel
Interfacial and Corrosion Processes in Molten Salts in Extreme Environments
Investigating Radiation-altered Corrosion in Liquid Lead
Investigation of Hydrogen Trapping by Irradiation-induced Defects in 316L Stainless Steel
Investigation on the Impact of Proton-irradiation on Vibrational Properties of LiNbO3 with Raman Spectroscopy
Ion Damage and Range in the Geometry of Nanomaterials (IDRAGON): A Step Forward to Design Innovative Nuclear Materials with Enhanced Radiation Tolerance
Ion Irradiation Study of Polymer Derived SiFeOC-C-SiC Composite
Modeling Zircaloy Oxidation and Hydridation under Irradiation: What Can be Learned from Physical Models and Simulations
Modelling the Primary Damage in Nickel and Nickel Based Alloys: Influence of Cascade Energy and Morphology in Displacement Cascades
Ni Oxidation by CO2 and Its Impact on D2 Ingress: A Nanoscale Study by In-Situ Atom Probe Tomography
On the Use of Corrosion Electrochemistry in Understanding Materials Corrosion in Molten FLiNaK Salts
One-dimensional Wormhole Morphology Induced by Molten Salt Corrosion in Ni-Cr Alloy
Quantification of the Oxidizing Effects of Neutron Activation Reactions in FLiBe
Quantifying Radiation Enhanced Diffusion in Model Oxides with Isotopic Tracers and Atom Probe Tomography
Radiation Stability of Nanostructured Ytrium Stabilized Zirconia
Study of Irradiation Defects Annealing in Thermally Grown Oxides by In Situ Raman Spectroscopy
Synergistic Processes in Irradiation-corrosion of Materials in High Temperature Water
Tailoring Alloy Microstructures to Measure Radiation Effects at Material Interfaces
Techniques for In-situ Crack Growth Testing and Monitoring in VTR Coolant Environments
The Coupled Effects of Irradiation and Corrosion on Materials
The Role of Surface and Interfacial Chemistry in Hydrogen Corrosion of Uranium
The Role of In Situ Analytical Electron Microscopy in Understanding the Behaviour of Structural Materials in Nuclear Power Systems: Examples and Opportunities
Understanding the Hydrogen Pickup Mechanism of M5Framatome under Ion Irradiation

Questions about ProgramMaster? Contact