ProgramMaster Logo
Conference Tools for 2025 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications III
Presentation Title Mechanical and irradiation behaviors in low-textured pyrolytic carbon
Author(s) Raphaelle David, Yongfeng Zhang
On-Site Speaker (Planned) Raphaelle David
Abstract Scope Pyrolytic carbons have attracted intensive research efforts because of their wide applications from the medical field to the nuclear industry. Among those, the TRISO particle fuel, which is considered as a leading fuel candidate for various advanced reactors, must sustain a very harsh environment during its lifetime. One of its layers, the buffer layer, is made of low-textured pyrocarbon and understanding its stress and irradiation response appears as necessary. Aided by molecular dynamics simulations, superelasticity followed by ductile fracture was observed for both tensile and compressive deformations. Under tension, reorientation and unfolding of the curved crystallites were identified as elastic deformation mechanisms while shear strain between individual graphene sheets was observed in the plastic range. Under compression, crystallites’ reorientation and decreasing interlayer spacing distance were the most prominent deformation mechanisms. Moreover, irradiation simulations are carried out to understand the microstructure’s evolution observed after TRISO particle irradiation.
Proceedings Inclusion? Planned:
Keywords Mechanical Properties, Computational Materials Science & Engineering, Other

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

A Machine Learning Approach for Predicting Nuclear Fuel Performance with Solid Fission Products
Additively manufactured transition layer design for fusion reactor components
Advancing SiC-SiC Cladding Technology To Support Nuclear Power Generation
Alloying Yttrium Hydride via Powder Metallurgy
Analyzing Advanced Composite Shield Materials for Fusion and Space Reactor Applications
Characterization and Post Irradiation Examination of Rapid Laser Chemical Vapor Deposited SiC Fibers
Computational Simulation on Irradiation Damage in GaAs-Based Betavoltaic Batteries
Corrosion Resistance of Amorphous Fe- and Ni-based Thermal Spray Coatings Exposed to Molten FLiNaK Salt Nuclear Reactor Coolant at 700 °C
Densification of 3D Printed Composite Ceramics via Spark Plasma Sintering
Determination of interface properties of W/EUROFER coating on steel substrate by phased array ultrasonic and fracture mechanical testing
Developing and testing silicon carbide composites for fusion-relevant conditions
Developing methods to predict failure and crack growth using small angle scattering techniques
Development of high-temperature-steam resistant UN via the addition of UB2
Development of Tungsten Composites as Plasma-Facing Materials by Doping Rare-Earth Boride Particulates
Development of tungsten fiber-reinforced tungsten composites for fusion application
Effects of Neutron Irradiation on the Three-Parameter Weibull Analysis of Graphite
Equivariant neural network force fields for 11-cation chloride molten salts system
Framatome’s SiCf/SiC LWR Cladding Design: Developments and Irradiation Programs
Impact of (U,Zr)C Carbon Stoichiometry on Thermal Properties
Irradiation tolerance and molten salt compatibility of beryllium carbide – a candidate high temperature moderator material.
Material bonding layered metallic and ceramic composites using continuous electric-field assisted sintering
Mechanical and irradiation behaviors in low-textured pyrolytic carbon
Microstructural evolution of tungsten boride neutron shielding materials under radiation
On the reduced damage tolerance of fine-grained nuclear graphite at elevated temperatures using in situ 4D tomographic imaging
Perspectives on Raman spectroscopy for carbon-based nuclear materials
Radiation resistance of nanostructured ferritic alloys produced via various methods
SiC-SiC composite cladding materials: effect of the manufacturing process on microstructure and physical properties
Silicon carbide composites for fusion applications
The Development of High-Temperature Continuous Fibre-Reinforced Ceramic Composite Materials for Molten Salt-Facing Environments
Thermal stability of powder metallurgically manufactured tungsten fiber-reinforced tungsten composites at 1450 °C
TRISO Coating Layer Failure Analysis
Tritium Breeder Composites for Fusion Applications
Understanding fission product behaviour in ion-implanted graphite

Questions about ProgramMaster? Contact programming@programmaster.org