Abstract
The radiation-induced amorphization of U3Si2 was investigated by in-situ transmission electron microscopy using 1 MeV Kr ion irradiation. Both arc-melted and sintered U3Si2 specimens were irradiated at room temperature to confirm the similarity in their responses to radiation. The sintered specimens were then irradiated at 350 °C and 550 °C up to 7.2 × 1015 ions/cm2 to examine their amorphization behavior under light water reactor (LWR) conditions. U3Si2 remains crystalline under irradiation at LWR temperatures. Oxidation of the material was observed at high irradiation doses.
Original language | English |
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Pages (from-to) | 168-173 |
Number of pages | 6 |
Journal | Journal of Nuclear Materials |
Volume | 484 |
DOIs | |
State | Published - Feb 1 2017 |
Externally published | Yes |
Funding
This work was funded by the Accident Tolerant Fuel High-Impact Problems (ATF HIP) of the U.S. Department of Energy (DOE)'s Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. The efforts involving Argonne National Laboratory, including the use of the IVEM-Tandem Facility, were sponsored under Contract no. DE-AC02-06CH11357 between UChicago Argonne, LLC and the U.S. Department of Energy. This work made use of the EPIC facility (NUANCE Center-Northwestern University), which has received support from the MRSEC program (NSFDMR-1121262) at the Materials Research Center; the Nanoscale Science and Engineering Center (NSFEEC-0647560) at the International Institute for Nanotechnology; and the State of Illinois, through the International Institute for Nanotechnology. Fabrication of the samples used in this work was supported by the U.S. Department of Energy, Office of Nuclear Energy. Fabrication was part of a collaboration led by Westinghouse Electric Company comprising several national laboratories, vendors, and universities awarded in response to the DE-FOA-0001063 funding opportunity. The authors would like to acknowledge the assistance of the support staff associated with the Fuels Applied Science Building at Idaho National Laboratory specifically Rita Hoggan for preparing samples for FIB liftouts.
Keywords
- Accident tolerant fuel
- In-situ TEM
- Ion irradiation
- Nuclear fuel
- Uranium silicide