A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)

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A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT). / Bachhav, Mukesh; Gan, Jian; Keiser, Dennis D.; Giglio, Jeffrey J.; Jadernas, Daniel; Leenaers, Ann; Van den Berghe, Sven.

In: Journal of Nuclear Materials, Vol. 528, No. 151853, 151853, 01.01.2020, p. 1-9.

Research output: Contribution to journalArticle

Harvard

Bachhav, M, Gan, J, Keiser, DD, Giglio, JJ, Jadernas, D, Leenaers, A & Van den Berghe, S 2020, 'A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)', Journal of Nuclear Materials, vol. 528, no. 151853, 151853, pp. 1-9. https://doi.org/10.1016/j.jnucmat.2019.151853

APA

Bachhav, M., Gan, J., Keiser, D. D., Giglio, J. J., Jadernas, D., Leenaers, A., & Van den Berghe, S. (2020). A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT). Journal of Nuclear Materials, 528(151853), 1-9. [151853]. https://doi.org/10.1016/j.jnucmat.2019.151853

Vancouver

Bachhav M, Gan J, Keiser DD, Giglio JJ, Jadernas D, Leenaers A et al. A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT). Journal of Nuclear Materials. 2020 Jan 1;528(151853):1-9. 151853. https://doi.org/10.1016/j.jnucmat.2019.151853

Author

Bachhav, Mukesh ; Gan, Jian ; Keiser, Dennis D. ; Giglio, Jeffrey J. ; Jadernas, Daniel ; Leenaers, Ann ; Van den Berghe, Sven. / A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT). In: Journal of Nuclear Materials. 2020 ; Vol. 528, No. 151853. pp. 1-9.

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@article{d37b1f5cee9e4aef9462a6ba92a46a47,
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 mm3) 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) UeMo fuel. APT is used to quantify the isotopes of 235U, 236U, 238U, 239Pu and 237Np for burnup calculation in the irradiated metallic Ue7Mo 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. This method provides U enrichment and local burnup with an unprecedented high spatial resolution based on quantification of isotopic ratios of U.",
keywords = "APT, irradiated fuel",
author = "Mukesh Bachhav and Jian Gan and Keiser, {Dennis D.} and Giglio, {Jeffrey J.} and Daniel Jadernas and Ann Leenaers and {Van den Berghe}, Sven",
note = "Score=10",
year = "2020",
month = "1",
day = "1",
doi = "10.1016/j.jnucmat.2019.151853",
language = "English",
volume = "528",
pages = "1--9",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",
number = "151853",

}

RIS - Download

TY - JOUR

T1 - A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)

AU - Bachhav, Mukesh

AU - Gan, Jian

AU - Keiser, Dennis D.

AU - Giglio, Jeffrey J.

AU - Jadernas, Daniel

AU - Leenaers, Ann

AU - Van den Berghe, Sven

N1 - Score=10

PY - 2020/1/1

Y1 - 2020/1/1

N2 - 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 mm3) 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) UeMo fuel. APT is used to quantify the isotopes of 235U, 236U, 238U, 239Pu and 237Np for burnup calculation in the irradiated metallic Ue7Mo 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. This method provides U enrichment and local burnup with an unprecedented high spatial resolution based on quantification of isotopic ratios of U.

AB - 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 mm3) 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) UeMo fuel. APT is used to quantify the isotopes of 235U, 236U, 238U, 239Pu and 237Np for burnup calculation in the irradiated metallic Ue7Mo 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. This method provides U enrichment and local burnup with an unprecedented high spatial resolution based on quantification of isotopic ratios of U.

KW - APT

KW - irradiated fuel

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/36037450

U2 - 10.1016/j.jnucmat.2019.151853

DO - 10.1016/j.jnucmat.2019.151853

M3 - Article

VL - 528

SP - 1

EP - 9

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

IS - 151853

M1 - 151853

ER -

ID: 5711274