| About this Abstract |
| Meeting |
MS&T24: Materials Science & Technology
|
| Symposium
|
Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments V
|
| Presentation Title |
Thermophysical Characterisation of Zirconium-Based Nuclear Materials |
| Author(s) |
Phylis Makurunje, Jack Callaghan, Abdullah Mamun, Michael Rushton, Simon Middleburgh |
| On-Site Speaker (Planned) |
Phylis Makurunje |
| Abstract Scope |
Nuclear thermal space reactors are designed to produce high specific impulse and thrust which are useful for propulsion of spacecrafts for Mars and deep-space missions. Thermal propulsion space reactors operate as heat exchangers for transferring heat from nuclear fuel to the propellant, and their operation in a mission is expected to lead to thermal variations during transient episodes. These temperature changes warrant that thermophysical properties of the cermet and/or ceramic fuel forms be studied. In the present work, thermophysical properties of zirconium-based materials were determined. Thermal conductivity and diffusivity studies were performed up to 500 °C on a laser flash analyser while thermal expansion studies were performed on an X-Ray diffractometer fitted with a heated stage. Findings, alongside microstructural characterisation results, informed thermo-mechanical studies that were performed to determine the structural integrity of the zirconium-based materials. |