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Meeting MS&T25: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments VI
Presentation Title High-Temperature Corrosion of Pure Vanadium in Molten Chloride Salt Environments
Author(s) Aaron Gabriel S. Penders, Stephanie C. Baldivieso, Alejandro R. Ballesteros, Ruchi Gakhar, Kaustubh K. Bawane
On-Site Speaker (Planned) Aaron Gabriel S. Penders
Abstract Scope Molten halide salts are pivotal in advanced molten salt reactor and fusion reactor designs due to their high-temperature heat transfer and thermal energy storage capabilities. Vanadium alloys, known for their high-temperature strength and radiation resistance, are emerging as promising candidate structural materials for these applications. Despite this, there is limited understanding of their corrosion performance under high temperature molten salt conditions. To that end, this study presents in-situ UV-VIS corrosion and post-corrosion electron microscopy analyses of pure vanadium subjected to LiCl-KCl eutectic molten salt, with and without 1 wt.% redox potential increasing EuCl3 additive, at 450 and 700 °C. UV-VIS spectroscopy reveals that vanadium proceeds through different oxidation states, as indicated by shifts in the absorption spectra, while electron microscopy captures microstructural, fine structure and elemental changes near the molten-salt interface. Understanding these interactions will enhance the structural alloy design principles for extreme molten salt environments.

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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