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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Special Topics in Nuclear Materials: Lessons Learned; Non-Energy Systems; and Coupled Extremes
Presentation Title Fabrication of Titanium-Containing Tri-Carbide Ultra-High Temperature Ceramics
Author(s) Ethan Charles Payne, Steven Zinkle
On-Site Speaker (Planned) Ethan Charles Payne
Abstract Scope Nuclear Thermal Propulsion (NTP) is proposed space propulsion technology capable of high specific impulse and thrust compared to chemical propulsion. In this system, a nuclear reactor core heats hydrogen gas propellant which is expanded through a nozzle at >2800 K to provide thrust. Potential reactor core materials include ultra-high temperature carbides comprised of transition metal cations like Ta, Nb, and Zr. Spark plasma sintering (SPS) provides a way to rapidly create high density products of these carbides from powder, allowing for the exploration of advanced bi- and tri-carbides. TiC is now being explored due in part to its favorable neutronic properties and low mass. (Ti, Zr, Nb)C, (Ti, Ta, Nb)C, and (Ti, Ta, Zr)C tri-carbides were fabricated via SPS, and characterized with density testing, scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS), x-ray diffraction (XRD) and mechanical testing to examine their sintering behavior, homogeneity and thermophysical properties.
Proceedings Inclusion? Planned:
Keywords High-Entropy Alloys, Other, Other

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advancing Radioisotope Heat Sources: Enhancing RPS for Extreme Environments
Atomistic Simulation of Thermal and Irradiation Creep Mechanisms in BCC-Fe and FCC-Ni using Defect Rate-Based Long-time Dynamics
Best Practices for Irradiation Experiment Design For Nuclear Fuels and Materials Research
Cavity Formation Induced by Swift Heavy Ion Irradiation in AlN/GaN
Comparison of Hardening and Microstructures of Structural Alloys Irradiated with Fast Neutrons and Dual Ions
Developing a High-Performance Cluster Dynamics Code: Challenges and Lessons Learned
Effect of Applied Stress on Radiation-Induced Loop and Raft Formation in a BCC Metal
Effect of Tensile Stress Gradients on the Multi-Length-Scale Microstructure in Thermal and Irradiation Creep of 316L Stainless Steel
Energy Dispersive X-Ray Spectroscopy (EDS) Induced Defects and Implantation Induced Impurities in Uranium Nitride (UN) and SIMFUEL Pellets
Fabrication of Titanium-Containing Tri-Carbide Ultra-High Temperature Ceramics
GIRAFFE – In Situ Material TestsUnder Fusion-Relevant Conditions
In-situ Electron Microscopy Characterization of Deformation Mechanisms of Inconel 718 Irradiated with Simultaneous High Energy Protons and Spallation Neutrons
Influence of Radiation Swelling on Residual Stresses and Measurement of Micromechanical Properties
Materials Research for High-Power Accelerator Beam-Intercepting Devices
Modeling Galvanic Drawdown Separations Technique
Phase Field Modeling of Irradiation-Induced Amorphous-to-Crystalline (A-C) Transformations in Structural Ceramics
Post Irradiation Examination and Administrative Lifetime Limits of Highly Irradiated Components at The Spallation Neutron Source
Small Scale Tests, Big Lessons Learned
The Recovery of Irradiation Damage for Zircaloy-2 and Zircaloy-4 following Irradiation at Higher Temperatures of 377-410°C

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