Abstract
In light water reactor (LWR) UO2 fuels, the evolution of volatile fission products is one of the critical areas of fuel behavior that is yet to be fully understood. In UO2 irradiated to high burnups, it is well known that most released fission gases come from the central region of the fuel as opposed to the highly porous high burnup structure (HBS) on the periphery of the pellets. However, fuels with and without interconnected bubble networks at the fuel center showed high to moderate release fractions, which conceals the mechanisms responsible for the gas release in the latter scenario. In this work, focused ion beam tomography was used to investigate the three-dimensional bubble structure in an irradiated LWR UO2 fuel pellet with high degree of fission gas retention so that the degree of bubble interconnection could be assessed. Six radial locations with different burnups and temperatures were serially sectioned and imaged to reconstruct the three-dimensional bubble structure. As expected, the highest porosity was observed at the periphery of the fuel (HBS). The porosity then decreased towards the pellet center, except for the centermost location. This location had a slightly higher porosity than its adjacent mid-radial location, which was attributed to the temperature difference between the two locations. This study provides a first-time volumetric evaluation of the porosity at different radial locations on a UO2 fuel pellet. During this investigation, no significant bubble interconnection was noted at any of the six radial locations.
Original language | English |
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Article number | 152053 |
Journal | Journal of Nuclear Materials |
Volume | 532 |
DOIs | |
State | Published - Apr 15 2020 |
Funding
The authors of this work are grateful to the many people involved in the specimen preparation and handling at the hot-cell and radiological facilities at Oak Ridge National Laboratory. Authors acknowledge Joseph Burns for burnup calculations, and Andrew Nelson, Tyler Gerczak, and Jason Harp for their support and critical review of the manuscript prior to publication. This research was supported in part by an appointment to the Oak Ridge National Laboratory Higher Education Research Experience Program, sponsored by the US Department of Energy and administered by the Oak Ridge Institute for Science and Education. The authors of this work are grateful to the many people involved in the specimen preparation and handling at the hot-cell and radiological facilities at Oak Ridge National Laboratory. Authors acknowledge Joseph Burns for burnup calculations, and Andrew Nelson, Tyler Gerczak, and Jason Harp for their support and critical review of the manuscript prior to publication. This research was supported in part by an appointment to the Oak Ridge National Laboratory Higher Education Research Experience Program , sponsored by the US Department of Energy and administered by the Oak Ridge Institute for Science and Education .
Funders | Funder number |
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Joseph Burns for burnup calculations | |
Oak Ridge National Laboratory | |
US Department of Energy | |
U.S. Department of Energy | |
Oak Ridge National Laboratory | |
Oak Ridge Institute for Science and Education |
Keywords
- 3D reconstruction
- FIB tomography
- Fission gas release
- High burnup fuel
- Uranium dioxide