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Meeting MS&T22: Materials Science & Technology
Symposium Ceramics for a New Generation of Nuclear Energy Systems and Applications
Presentation Title Environmental Degradation of Ceramic Materials in Nuclear Energy Systems
Author(s) Hwasung Yeom, Kumar Sridharan
On-Site Speaker (Planned) Hwasung Yeom
Abstract Scope Ceramics have been considered as fuel forms, structural and coating materials, and for waste storage in nuclear energy systems. For example, environmental degradation of ceramic materials such as SiC/SiCf composite, graphite, C/Cf composite, and borosilicate glass have been investigated for applications including accident tolerant fuel cladding, moderator material, control rod sheath, and waste immobilization. Ceramic coatings have been proposed for Zr-alloy cladding to improve the oxidation resistance in light water reactors (LWRs), and for minimizing corrosion and liquid metal embrittlement of steels in lead fast reactors (LFRs). The high temperature gas-cooled reactor (HTGR) also provides unique opportunities for use of ceramics. In molten salt reactors (MSRs), ceramic coatings may be beneficial for corrosion resistance and as diffusion barriers for tritium. Ceramic coatings have also been considered for neutron radiation shielding. With these applications as basis, the presentation will cover the scope and opportunities for ceramic materials in nuclear energy applications.

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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