ProgramMaster Logo
Conference Tools for MS&T22: Materials Science & Technology
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting MS&T22: Materials Science & Technology
Symposium Ceramics for a New Generation of Nuclear Energy Systems and Applications
Presentation Title Radiation Effects in Single-crystal High-entropy Oxides
Author(s) Candice Kinsler-Fedon, Lauren Nuckols, Anamul H. Mir, Christopher Nelson, David Mandrus, Yanwen Zhang, Veerle Keppens, William J. Weber
On-Site Speaker (Planned) William J. Weber
Abstract Scope High-entropy pyrochlore oxides have recently gained recognition for their low thermal conductivity and tunable mechanical capabilities, but little is known about their irradiation behavior. In this work, the heavy-ion irradiation response of single-crystal, high-entropy oxides (HEO) with the pyrochlore structure have been investigated. The damage accumulation behavior at 300 K due to 4 MeV Au ion irradiation of a <100>-oriented HEO single crystal has been investigated by Rutherford backscattering spectrometry in channeling mode. Transmission electron microscopy with in situ irradiation using 600 keV Xe ions has been employed to determine the temperature dependence of amorphization in the same HEO composition. In another HEO single-crystal composition, the amorphization due to 23 MeV Ni ions has been characterized by Raman spectroscopy. The results obtained on these HEO pyrochlores are compared to those of single-component pyrochlores.

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

Questions about ProgramMaster? Contact programming@programmaster.org