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Meeting MS&T22: Materials Science & Technology
Symposium Ceramics for a New Generation of Nuclear Energy Systems and Applications
Presentation Title Phonon Broadening in High Entropy Ceramic Carbide
Author(s) Linu Malakkal, Kaustubh K Bawane, Cody A Dennet, Zilong Hua, Lingfeng He, Yongfeng Lu, Bai Cui
On-Site Speaker (Planned) Linu Malakkal
Abstract Scope In the quest for novel irradiation-resistant and high-temperature tolerant ceramic materials for nuclear applications, the high entropy ceramic carbide materials with outstanding properties are a promising material class. At high temperatures, material properties such as thermal stability, thermodynamic, elastic property, and thermal conductivity are critically influenced by atomic vibrations (phonons). In a crystalline ceramic, carbides with an extreme disorder of cations can induce significant phonon scattering and broadening, owing to the inherently present mass and force constant variances. Despite the importance, phonon scattering and broadening in high entropy ceramic carbide are still lacking. Hence, in this work, we use the abinitio calculations to systematically investigate the impact of the mass and force constant variance on the phonon spectral function of face-centered cubic HECC, from binaries up to 5-component high entropy alloys, addressing the key question of how chemical complexity impacts the phonons

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Physics-Based Cluster Dynamics Model of Radiation-Enhanced Growth of Oxides
Additive Manufacturing of Ceramics for Nuclear Applications
Bismuth Loaded Carbon Foam as an Effective Radio Iodine Sorbent
Characterization of Radiation Effects in Ceramics with Spallation Neutron Probes
Characterizing Effects of Aging Bismuth Laden Sorbents in NOx Atmosphere for Radioiodine Capture
Cluster Dynamics Simulations of Point Defects and Fission Gas Evolution in Irradiated Ceramic Nuclear Fuels
Comparison of ZrC-TZM Mechanical and Structural Properties Before and After Extended Carbon Exposure
Corrosion of SiC in Molten Salt and Liquid Lead
Development of Novel TRU-containing Ceramics for Nuclear Waste Immobilization
Environmental Degradation of Ceramic Materials in Nuclear Energy Systems
Fabrication and Properties of Sintered Yttrium Hydride
Integration of Nuclear Fuel and Embedded Sensors within Additively Manufactured SiC Components
J-1: Development and Characterization of Ga/Ta Doped Li7La3Zr2O12 for Direct LiT Electrolysis
J-2: Evaluation of In-Flow Mechanical Robustness of Metal-Functionalized Porous Silica Materials
Microstructural Evolution in Ceramic Nuclear Fuels and their Surrogates under Irradiation
Modeling Vibrational Modes in Raman Spectra of ThO2
Phonon Broadening in High Entropy Ceramic Carbide
Radiation Damage of Ion-irradiated High Entropy Ceramics
Radiation Effects in Single-crystal High-entropy Oxides
SiC Oxidation and Irradiation Resistance in Advanced Nuclear Reactor TRISO Fuel
Single Component Variations in Glass Ceramic Waste Forms
Sulfur Retention of Low Activity Waste Glasses
Synthesis and Characterization of Super Occluded LiCl-KCl in Zeolite-4A as a Chloride Salt Waste Form Intermediate

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