A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)
Abstract
A novel approach is presented to determine the local burnup in irradiated fuels using isotopic quantification obtained by Atom Probe Tomography (APT). Considering the volume of sample used (<100 μm3) for APT experiments using the lift-out process in a scanning electron microscope equipped with a Focused Ion Beam (FIB), the presented method determines the local burnup from a nuclear fuel, where a minimal amount of waste is produced. In this work, three samples were analyzed with different burnup conditions: as received low enriched 19.8% U-235, intermediate burnup (~52% U-235 fissioned) and high burnup (~69% U-235 fissioned) U–Mo fuel. APT is used to quantify the isotopes of 235U, 236U, 238U, 239Pu and 237Np for burnup calculation in the irradiated metallic U–7Mo dispersion fuel. The equation used to estimate the burnup of fuels is derived by considering that the initial counts of U is equal to the sum of remaining atoms of U isotopes and all the U reactions undergone during irradiation. Here, this method provides U enrichment and local burnup with an unprecedented high spatial resolution based on quantification of isotopic ratios of U.
- Authors:
-
[1];
[1];
[1];
[1];
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Studsvik Nuclear AB, Nyköping (Sweden)
- SCK.CEN, Nuclear Materials Science Inst., Mol (Belgium)
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1572466
- Alternate Identifier(s):
- OSTI ID: 1776026
- Report Number(s):
- INL/JOU-19-52754-Rev000
Journal ID: ISSN 0022-3115; TRN: US2001303
- Grant/Contract Number:
- AC07-05ID14517
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 528; Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; Atom Probe Tomography; Isotopes; burnup; metallic fuel
Citation Formats
Bachhav, Mukesh, Gan, Jian, Keiser, Jr., Dennis D., Giglio, Jeffrey J., Jädernäs, Daniel, Leenaers, Ann, and Van den Berghe, Sven. A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT). United States: N. p., 2019.
Web. doi:10.1016/j.jnucmat.2019.151853.
Bachhav, Mukesh, Gan, Jian, Keiser, Jr., Dennis D., Giglio, Jeffrey J., Jädernäs, Daniel, Leenaers, Ann, & Van den Berghe, Sven. A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT). United States. https://doi.org/10.1016/j.jnucmat.2019.151853
Bachhav, Mukesh, Gan, Jian, Keiser, Jr., Dennis D., Giglio, Jeffrey J., Jädernäs, Daniel, Leenaers, Ann, and Van den Berghe, Sven. Tue .
"A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)". United States. https://doi.org/10.1016/j.jnucmat.2019.151853. https://www.osti.gov/servlets/purl/1572466.
@article{osti_1572466,
title = {A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)},
author = {Bachhav, Mukesh and Gan, Jian and Keiser, Jr., Dennis D. and Giglio, Jeffrey J. and Jädernäs, Daniel and Leenaers, Ann and Van den Berghe, Sven},
abstractNote = {A novel approach is presented to determine the local burnup in irradiated fuels using isotopic quantification obtained by Atom Probe Tomography (APT). Considering the volume of sample used (<100 μm3) for APT experiments using the lift-out process in a scanning electron microscope equipped with a Focused Ion Beam (FIB), the presented method determines the local burnup from a nuclear fuel, where a minimal amount of waste is produced. In this work, three samples were analyzed with different burnup conditions: as received low enriched 19.8% U-235, intermediate burnup (~52% U-235 fissioned) and high burnup (~69% U-235 fissioned) U–Mo fuel. APT is used to quantify the isotopes of 235U, 236U, 238U, 239Pu and 237Np for burnup calculation in the irradiated metallic U–7Mo dispersion fuel. The equation used to estimate the burnup of fuels is derived by considering that the initial counts of U is equal to the sum of remaining atoms of U isotopes and all the U reactions undergone during irradiation. Here, this method provides U enrichment and local burnup with an unprecedented high spatial resolution based on quantification of isotopic ratios of U.},
doi = {10.1016/j.jnucmat.2019.151853},
journal = {Journal of Nuclear Materials},
number = C,
volume = 528,
place = {United States},
year = {Tue Oct 15 00:00:00 EDT 2019},
month = {Tue Oct 15 00:00:00 EDT 2019}
}
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Figures / Tables:
Figure 1: SEM images of unirradiated (left), intermediate burnup (middle) and high burnup sample (right) of U-7Mo coated with ZrN and embedded in Al matrix.