Abstract Title
Transverse Rupture Strength of CeO2 as a Surrogate Nuclear Fuel
Additional Funding Sources
The project described was supported by the Research Experience for Undergraduates Program Site: Materials for Society at Boise State University under Award No. 1658076.
Abstract
Nuclear power supplies 20 percent of the US energy demand and is steadily increasing. This has created a growing interest in fully understanding the relationship between microstructure and performance of ceramic nuclear fuels. Plutonia (PuO2), recovered as a by-product from the fission of uranium, is of particular interest due to its use in fast thermal and neutron reactors as well as radioisotope thermoelectric generators. Because of the significant challenges involved in studying highly radioactive materials, cerium oxide (CeO2) is being investigated as a surrogate nuclear fuel for PuO2 due to having similar chemical and thermophysical properties such as ionic size, melting temperature, and crystal structure. The objective of this study is to better understand the mechanical properties of CeO2 through developing and validating a testing method for its flexural strength. The testing methods were validated first using commercially available alumina (Al2O3), with known properties, as a benchmark. CeO2 pellets were fabricated and characterized via scanning electron microscopy and x-ray diffraction prior to measuring flexural strength.
Transverse Rupture Strength of CeO2 as a Surrogate Nuclear Fuel
Nuclear power supplies 20 percent of the US energy demand and is steadily increasing. This has created a growing interest in fully understanding the relationship between microstructure and performance of ceramic nuclear fuels. Plutonia (PuO2), recovered as a by-product from the fission of uranium, is of particular interest due to its use in fast thermal and neutron reactors as well as radioisotope thermoelectric generators. Because of the significant challenges involved in studying highly radioactive materials, cerium oxide (CeO2) is being investigated as a surrogate nuclear fuel for PuO2 due to having similar chemical and thermophysical properties such as ionic size, melting temperature, and crystal structure. The objective of this study is to better understand the mechanical properties of CeO2 through developing and validating a testing method for its flexural strength. The testing methods were validated first using commercially available alumina (Al2O3), with known properties, as a benchmark. CeO2 pellets were fabricated and characterized via scanning electron microscopy and x-ray diffraction prior to measuring flexural strength.
Comments
W36