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Meeting MS&T25: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments VI
Presentation Title Corrosion of Ni-based alloys in Light Water Reactor Environment: An In-situ Bragg Coherent Diffraction Imaging approach
Author(s) Sayantan Mondal, David Simonne, Riley Hultquist, Ericmoore Elijah Jossou
On-Site Speaker (Planned) Sayantan Mondal
Abstract Scope Structural materials such as stainless steel and nickel-based alloys, used in industrial pressure vessels and nuclear reactors, are routinely exposed to extreme environments characterized by high temperatures, irradiation, mechanical stresses, and corrosive conditions, including corrosion, radiolysis, and hydriding media. These challenges require immediate attention to ensure the life extension of existing light water reactors (LWRs) and the successful deployment of the next generation of reactors. In this work, we present results from Bragg Coherent Diffraction Imaging (BCDI) to investigate the temporal evolution of corrosion-induced lattice defects in a model Ni-based alloy under simulated LWR conditions. This talk will highlight the formation of lattice defects during prolonged exposure to normal water chemistry, as well as the radiolytic effects of the intense X-ray beam used during the BCDI measurements. These fundamental insights will inform the design of corrosion-resistant alloys, extending service lifetimes and improving the cost effectiveness of reactor operations.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Time Dependent Multiaxial Inelastic Constitutive Model for Nuclear Graphite
Bridging Distributed Autonomous Platforms for Materials Innovation
Comparative Assessment of Biaxial Creep Anisotropy in ZIRLOŽ and HANA-4 Zirconium Alloys: Influence of Microstructure and Processing
Corrosion of Ni-based alloys in Light Water Reactor Environment: An In-situ Bragg Coherent Diffraction Imaging approach
Coupled Experimental and Modeling of the Interactions Between Dislocations, Precipitates, and Grain Boundaries from Atomic to Mesoscale
Development, Validation, and Uncertainty Quantification of a BISON Model for Pd Penetration in TRISO Particle Fuels
Gamma Ray Shielding Performance of 3D Printed Polymers
High-Temperature Corrosion of Pure Vanadium in Molten Chloride Salt Environments
In-Situ and 3D Measurements of Dynamic Processes in Nuclear Materials Utilizing Synchrotron High-energy X-rays
Influence of Point Defect Evolution on Thermal Conductivity Degradation and Fission Gas Behavior in UO₂ Under Accelerated Irradiation
Quantifying Amorphous Fractions using Different Characterization Techniques
Radiation-Induced Amorphization in WO₃ and MoO₃: Structural Response
Statistical Effects of Carbon on Primary Radiation Damage and Initial Clustering of Defects in Austenitic Stainless Steel
Strain Field Evolution Around MX Precipitates in a Ferrite Matrix After Neutron Irradiation at 490°C to 7.4 dpa
Ultra-High Temperature Thermal Characterization of Materials for Nuclear Applications
Unique Aspects of Coupling Experiment and Modeling in Understanding Irradiation Behavior of Nuclear Materials

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