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Meeting MS&T25: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments VI
Presentation Title Strain Field Evolution Around MX Precipitates in a Ferrite Matrix After Neutron Irradiation at 490°C to 7.4 dpa
Author(s) Emily Proehl, Yan-Ru Lin, Weicheng Zhong, Steven J. Zinkle
On-Site Speaker (Planned) Emily Proehl
Abstract Scope Engineering a high number density of nanoscale precipitates is a leading strategy to introduce radiation tolerance in nuclear structural alloys through the concept of “sink strength”, or the propensity of a microstructural feature to facilitate point defect recombination. The strain field around precipitates’ interfaces is directly related to the capture radius to attract point defects and point defect clusters, allowing for recombination. In this work, model ferritic alloys containing nanoscale TaC and TaN MX-type precipitates, respectively, were investigated before and after neutron irradiation in the High Flux Isotope Reactor to 7.4 dpa at 490°C. Geometric phase analysis (GPA) strain mapping around the MX precipitates was performed using atomic resolution images from a Cs-corrected scanning transmission electron microscope (STEM), as well as atomic resolution chemical mapping. MX precipitate stability, strain field evolution, and defect interaction were observed and corresponding implications on alloy design will be discussed.

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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