Radial Characterization of As-Irradiated and Post-LOCA Tested High Burnup UO2 Fuel Using SEM and S/TEM-EDS

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

High burnup UO2 fuel under steady-state irradiation experiences microstructural changes including subgrain formation and fission gas bubbles production. The fuel is susceptible to fragmentation, pulverization and eventual dispersal under loss-of-coolant accident (LOCA) conditions. Analysis is needed to quantify inter- and intragranular bubble density to determine a correlation of bubble radial distribution and aid in understanding the driving mechanisms controlling restructuring and high burnup structure formation. Two fuel samples were analyzed in the as-irradiated and simulated LOCA test condition with an average sample burnup of 69 and 77 MWd/kgU. Particle measurements from the scanning electron microscopy (SEM) data revealed an overall decrease in pore number density and increase in average pore area from the fuel periphery to centerline in all samples. However, an increase in pore number density is observed approximately at the fuel mid-radius (0.60 r/r0) before decreasing again towards the fuel center. An initial image processing technique was performed to identify inter- and intragranular pores and displayed primarily intergranular pores at the fuel periphery which decrease rapidly towards the center. Scanning/transmission electron microscopy (S/TEM) with energy-dispersive X-ray spectroscopy (EDS) data exhibited a similar trend observed with the pore SEM data. Further analysis is ongoing to identify inter- and intragranular bubbles using the S/TEM-EDS data and the proposed image processing technique.

Original languageEnglish
Title of host publicationProceedings of the TopFuel 2025
Subtitle of host publicationNuclear Reactor Fuel Performance Conference
PublisherAmerican Nuclear Society
Pages1570-1578
Number of pages9
ISBN (Electronic)9780894482281
DOIs
StatePublished - 2025
EventTopFuel 2025: Nuclear Reactor Fuel Performance Conference - Nashville, United States
Duration: Oct 5 2025Oct 9 2025

Publication series

NameProceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference

Conference

ConferenceTopFuel 2025: Nuclear Reactor Fuel Performance Conference
Country/TerritoryUnited States
CityNashville
Period10/5/2510/9/25

Funding

The author is grateful for the facilities (Irradiated Fuels Examination Laboratory and Low Activation Materials Development and Analysis at ORNL) and the corresponding staff and support personnel for their assistance in this project. This work was funded by the U.S. Department of Energy, Advanced Fuels Campaign, and UT-Battelle (UTB) sub-contract UTB-CW41490, in addition to UTB JF GC 4000101051.

Keywords

  • High burnup fuel
  • STEM
  • xenon bubbles

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