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Title: 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 μm 3) 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:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1];  [2];  [3];  [3]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Studsvik Nuclear AB, Nyköping (Sweden)
  3. 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
Report Number(s):
INL/JOU-19-52754-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: 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. doi: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. doi:10.1016/j.jnucmat.2019.151853.
@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 = {2019},
month = {10}
}

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This content will become publicly available on October 15, 2020
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