Abstract
Observations from a scanning electron microscopy examination of irradiated U-10Zr fuel are presented. The sample studied had a local burnup of 5.7 atom percent and a local inner cladding temperature of 615 °C. This examination by electron microscopy has concentrated on producing data relevant to facilitating a better understanding of Zr redistribution in irradiated U-10Zr fuel and on a better understanding of the complex microstructure present in fuel cladding chemical interaction (FCCI) layers. The presented zirconium redistribution data supplements the existing literature by providing a data set at these particular local conditions. In addition to FCCI layers that are readily visible in optical microscopy, this examination has revealed lanthanide degradation of the cladding by what appears to be a grain boundary facilitated pathway. Precipitates of fission produced Pd-lanthanide compounds were observed in the fuel. Precipitated regions with elevated Mo and elevated W content were also observed in the HT-9 cladding of this sample.
Original language | English |
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Pages (from-to) | 227-239 |
Number of pages | 13 |
Journal | Journal of Nuclear Materials |
Volume | 494 |
DOIs | |
State | Published - Oct 2017 |
Externally published | Yes |
Funding
This work was supported by the U.S. Department of Energy, Advanced Fuels Campaign of the Fuel Cycle R&D program in the Office of Nuclear Energy.
Keywords
- Fuel cladding chemical interaction (FCCI)
- Irradiated fuel
- Scanning electron microscopy
- U-10Zr
- Zirconium redistribution