Fracture Strength Determination Methods for Ceramic Materials Applied to Uranium Dioxide

  • Andrew T. Nelson
  • , Chinthaka M. Silva
  • , A Lupercio
  • , E Moshkelgosha
  • , Riley Winters
  • , C Doyle
  • , Shen Dillon
  • , Brent J. Heuser
  • , Brian Jaques

Research output: Other contributionTechnical Report

Abstract

The Advanced Fuels Campaign is currently focusing on development of accident-tolerant fuels that possess a range of property modifications intended to improve fuel performance during accident and transient conditions as well as extend license limits to burnups beyond 62 MWd/kgU. Both of these drivers have identified understanding and mitigating fuel cracking as a key performance criterion. Small-scale cantilever beam testing has been identified as a plausible method by which to collect fracture data for UO2 as a function of chemical and structural evolutions introduced either during fabrication or irradiation. While this method has been found to be capable of providing data that are in reasonable agreement with literature for unirradiated UO2, the inherently small sample volumes that can be sampled limit its ability to capture the statistical nature of mechanisms that govern the fracture of brittle ceramics. A biaxial flexure strength test was developed to be used for unirradiated UO2. This method is standard in the community, but no systems presently in use at national laboratories, universities, or private companies are available to be used for nuclear fuel materials. This report describes the operation and benchmarking of this system, which has been validated for a number of common oxides. Future work will extend this system to characterization of both doped UO2 and other relevant microstructural modifications that can also be measured using small-scale cantilever beam testing. Comparison of datasets collected using both methods will allow the overall applicability of small-scale techniques to be assessed and provide confidence or bounds on their use for irradiated fuels.
Original languageEnglish
Place of PublicationUnited States
DOIs
StatePublished - 2020

Keywords

  • 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Fingerprint

Dive into the research topics of 'Fracture Strength Determination Methods for Ceramic Materials Applied to Uranium Dioxide'. Together they form a unique fingerprint.

Cite this