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Meeting MS&T25: Materials Science & Technology
Symposium Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments VI
Presentation Title Ultra-High Temperature Thermal Characterization of Materials for Nuclear Applications
Author(s) Heng Wang, Florian Linseis
On-Site Speaker (Planned) Heng Wang
Abstract Scope Accurate measurement of thermophysical properties—such as thermal diffusivity, thermal conductivity, thermal expansion, and simultaneous thermal analysis (STA)—is critical for the development of materials used in nuclear applications. In this paper, we present a suite of advanced instruments featuring tungsten heating elements, capable of performing thermal diffusivity measurements via Laser Flash Analysis (LFA), thermal expansion measurements using a push-rod dilatometer, and simultaneous DSC/TGA analysis at temperatures up to 2400 °C. These ultra-high temperature instruments have been utilized in several key projects to obtain property data that are otherwise difficult to obtain.

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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