Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9
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. Furthermore, precipitated regions with elevated Mo and elevated W content were also observed in the HT-9 cladding of this sample.
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5); USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1481288
- Alternate Identifier(s):
- OSTI ID: 1495575
- Report Number(s):
- INL/JOU-17-42679-Rev000
Journal ID: ISSN 0022-3115
- Grant/Contract Number:
- AC07-05ID14517
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 494; Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Scanning Electron Microscopy; Irradiated U-10Zr; Fast Flux Test Facility Irradiated; Fuel Cladding Chemical Interaction; Zr redistribution; HT-9
Citation Formats
Harp, Jason M., Porter, Douglas L., Miller, Brandon D., Trowbridge, Tammy L., and Carmack, William J. Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. United States: N. p., 2017.
Web. doi:10.1016/j.jnucmat.2017.07.040.
Harp, Jason M., Porter, Douglas L., Miller, Brandon D., Trowbridge, Tammy L., & Carmack, William J. Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9. United States. https://doi.org/10.1016/j.jnucmat.2017.07.040
Harp, Jason M., Porter, Douglas L., Miller, Brandon D., Trowbridge, Tammy L., and Carmack, William J. Sat .
"Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9". United States. https://doi.org/10.1016/j.jnucmat.2017.07.040. https://www.osti.gov/servlets/purl/1481288.
@article{osti_1481288,
title = {Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9},
author = {Harp, Jason M. and Porter, Douglas L. and Miller, Brandon D. and Trowbridge, Tammy L. and Carmack, William J.},
abstractNote = {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. Furthermore, precipitated regions with elevated Mo and elevated W content were also observed in the HT-9 cladding of this sample.},
doi = {10.1016/j.jnucmat.2017.07.040},
journal = {Journal of Nuclear Materials},
number = C,
volume = 494,
place = {United States},
year = {Sat Jul 22 00:00:00 EDT 2017},
month = {Sat Jul 22 00:00:00 EDT 2017}
}
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