Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel

Salvato, D.; Smith, C. A.; Ye, B.; Mei, Z. -G.; Yacout, A. M.; Van Eyken, J.; Miller, B. D.; Keiser, D. D.; Glagolenko, I. Y.; Giglio, J. J.; Robinson, A. B.; Leenaers, A.; Wight, J.; Henley, J. L.

doi:10.1016/j.nme.2023.101469

Title: Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel

Journal Article · 01 September 2023 · Nuclear Materials and Energy

DOI: https://doi.org/10.1016/j.nme.2023.101469 · OSTI ID:1987921

; Smith, C. A.; Ye, B.;

; Yacout, A. M.; Van Eyken, J.; Miller, B. D.;

; Glagolenko, I. Y.; Giglio, J. J.; Robinson, A. B.; Leenaers, A.;

; Henley, J. L.

Not Available

View Journal Article

Cite

Export

Save

Research Organization:: Argonne National Laboratory (ANL), Argonne, IL (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE; USDOE Idaho Operations Office (IO); USDOE National Nuclear Security Administration (NNSA), Office of Counter-terrorism and Counter-nonproliferation; USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC02-06CH11357; AC07-05ID14517

OSTI ID:: 1987921

Report Number(s):: INL/JOU--22-70209-Rev000; S2352179123001084; 101469; PII: S2352179123001084

Journal Information:: Nuclear Materials and Energy, Journal Name: Nuclear Materials and Energy Journal Issue: C Vol. 36; ISSN 2352-1791

Publisher:: ElsevierCopyright Statement

Country of Publication:: Netherlands

Language:: English

References (37)

CASINO V2.42—A Fast and Easy-to-use Modeling Tool for Scanning Electron Microscopy and Microanalysis Users Drouin, Dominique; Couture, Alexandre Réal; Joly, Dany Scanning, Vol. 29, Issue 3 https://doi.org/10.1002/sca.20000	journal	January 2007
Does your SEM Really tell the truth?-how would you know? Part 1 Postek, Michael T.; Vladár, András E. Scanning, Vol. 35, Issue 6 https://doi.org/10.1002/sca.21075	journal	February 2013
CASINO: A new monte carlo code in C language for electron beam interaction -part I: Description of the program Hovington, Pierre; Drouin, Dominique; Gauvin, Raynald Scanning, Vol. 19, Issue 1 https://doi.org/10.1002/sca.4950190101	journal	January 1997
CASINO: A new monte carlo code in C language for electron beam interactions-part II: Tabulated values of the mott cross section Drouin, Dominique; Hovington, Pierre; Gauvin, Raynald Scanning, Vol. 19, Issue 1 https://doi.org/10.1002/sca.4950190103	journal	January 1997
CASINO: A new monte Carlo code in C language for electron beam interactions-part III: Stopping power at low energies Hovington, Pierre; Drouin, Dominique; Gauvin, Raynald Scanning, Vol. 19, Issue 1 https://doi.org/10.1002/sca.4950190104	journal	January 1997
New approach for measuring interconnectivity of fission gas pores in nuclear fuels from 2D micrographs Smith, Charlyne A.; Cui, Yiming; Miller, Brandon Journal of Materials Science, Vol. 56, Issue 1 https://doi.org/10.1007/s10853-020-05368-x	journal	September 2020
Detailed characterisation of the rim microstructure in PWR fuels in the burn-up range 40–67 GWd/tM Spino, J.; Vennix, K.; Coquerelle, M. Journal of Nuclear Materials, Vol. 231, Issue 3 https://doi.org/10.1016/0022-3115(96)00374-1	journal	August 1996
Multiple voltage electron probe microanalysis of fission gas bubbles in irradiated nuclear fuel Verwerft, M. Journal of Nuclear Materials, Vol. 282, Issue 2-3 https://doi.org/10.1016/S0022-3115(00)00421-9	journal	December 2000
Stereological evolution of the rim structure in PWR-fuels at prolonged irradiation: Dependencies with burn-up and temperature Spino, J.; Stalios, A. D.; Santa Cruz, H. Journal of Nuclear Materials, Vol. 354, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2006.02.095	journal	August 2006
Transmission electron microscopy investigation of irradiated U–7wt%Mo dispersion fuel Van den Berghe, S.; Van Renterghem, W.; Leenaers, A. Journal of Nuclear Materials, Vol. 375, Issue 3 https://doi.org/10.1016/j.jnucmat.2007.12.006	journal	April 2008
Transmission electron microscopy characterization of irradiated U–7Mo/Al–2Si dispersion fuel Gan, J.; Keiser, D. D.; Wachs, D. M. Journal of Nuclear Materials, Vol. 396, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2009.11.015	journal	January 2010
Advantages and disadvantages of using a focused ion beam to prepare TEM samples from irradiated U–10Mo monolithic nuclear fuel Miller, B. D.; Gan, J.; Madden, J. Journal of Nuclear Materials, Vol. 424, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.01.022	journal	May 2012
TEM characterization of U–7Mo/Al–2Si dispersion fuel irradiated to intermediate and high fission densities Gan, J.; Keiser, D. D.; Miller, B. D. Journal of Nuclear Materials, Vol. 424, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.02.001	journal	May 2012
Microstructural characterization of irradiated U–7Mo/Al–5Si dispersion fuel to high fission density Gan, J.; Miller, B. D.; Keiser, D. D. Journal of Nuclear Materials, Vol. 454, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.08.052	journal	November 2014
Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7 wt%Mo dispersion fuels Miller, B. D.; Gan, J.; Keiser, D. D. Journal of Nuclear Materials, Vol. 458 https://doi.org/10.1016/j.jnucmat.2014.12.012	journal	March 2015
Thermal stability of fission gas bubble superlattice in irradiated U–10Mo fuel Gan, J.; Keiser, D. D.; Miller, B. D. Journal of Nuclear Materials, Vol. 464 https://doi.org/10.1016/j.jnucmat.2015.04.023	journal	September 2015
Analysis of irradiated U-7wt%Mo dispersion fuel microstructures using automated image processing Collette, R.; King, J.; Buesch, C. Journal of Nuclear Materials, Vol. 475 https://doi.org/10.1016/j.jnucmat.2016.03.028	journal	July 2016
High burn-up structure of U(Mo) dispersion fuel Leenaers, A.; Van Renterghem, W.; Van den Berghe, S. Journal of Nuclear Materials, Vol. 476 https://doi.org/10.1016/j.jnucmat.2016.04.035	journal	August 2016
Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels Cappia, F.; Pizzocri, D.; Schubert, A. Journal of Nuclear Materials, Vol. 480 https://doi.org/10.1016/j.jnucmat.2016.08.010	journal	November 2016
Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density Gan, J.; Miller, B. D.; Keiser, D. D. Journal of Nuclear Materials, Vol. 492 https://doi.org/10.1016/j.jnucmat.2017.05.035	journal	August 2017
Pore pressure estimation in irradiated UMo Salvato, D.; Leenaers, A.; Van den Berghe, S. Journal of Nuclear Materials, Vol. 510 https://doi.org/10.1016/j.jnucmat.2018.08.039	journal	November 2018
Post-irradiation examinations of UO 2 composites as part of the Accident Tolerant Fuels Campaign Cappia, F.; Harp, J. M.; McCoy, K. Journal of Nuclear Materials, Vol. 517 https://doi.org/10.1016/j.jnucmat.2019.01.050	journal	April 2019
Microstructural response of the fuel phase in U-7Mo dispersion fuel irradiated at different powers Smith, Charlyne A.; Miller, Brandon D.; Keiser, Dennis Journal of Nuclear Materials, Vol. 542 https://doi.org/10.1016/j.jnucmat.2020.152481	journal	December 2020
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel Genoni, R.; Pizzocri, D.; Antonello, F. Journal of Nuclear Materials, Vol. 548 https://doi.org/10.1016/j.jnucmat.2021.152843	journal	May 2021
Microstructural dependence on fuel matrix composition in irradiated U-Mo dispersion fuels Smith, Charlyne A.; Keiser, Dennis D.; Miller, Brandon D. Journal of Nuclear Materials, Vol. 550 https://doi.org/10.1016/j.jnucmat.2021.152943	journal	July 2021
Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing Cappia, F.; Wright, K.; Frazer, D. Journal of Nuclear Materials, Vol. 569 https://doi.org/10.1016/j.jnucmat.2022.153881	journal	October 2022
Benefits of utilizing CellProfiler as a characterization tool for U–10Mo nuclear fuel Collette, R.; Douglas, J.; Patterson, L. Materials Characterization, Vol. 105 https://doi.org/10.1016/j.matchar.2015.03.034	journal	July 2015
Fission gas bubble identification using MATLAB's image processing toolbox Collette, R.; King, J.; Keiser, D. Materials Characterization, Vol. 118 https://doi.org/10.1016/j.matchar.2016.06.010	journal	August 2016
Characterization of fission gas bubbles in irradiated U-10Mo fuel Casella, Andrew M.; Burkes, Douglas E.; MacFarlan, Paul J. Materials Characterization, Vol. 131 https://doi.org/10.1016/j.matchar.2017.06.007	journal	September 2017
Comparison of manual and automated image analysis techniques for characterization of fission gas pores in irradiated U-Mo fuels Smith, Charlyne A.; Keiser, Dennis D.; Miller, Brandon D. Micron, Vol. 119 https://doi.org/10.1016/j.micron.2019.01.008	journal	April 2019
Focused ion beam–scanning electron microscope examination of high burn-up UO2 in the center of a pellet Noirot, J.; Zacharie-Aubrun, I.; Blay, T. Nuclear Engineering and Technology, Vol. 50, Issue 2 https://doi.org/10.1016/j.net.2017.12.002	journal	March 2018
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms Pizzocri, D.; Genoni, R.; Antonello, F. Nuclear Engineering and Technology, Vol. 53, Issue 9 https://doi.org/10.1016/j.net.2021.03.012	journal	September 2021
NIH Image to ImageJ: 25 years of image analysis Schneider, Caroline A.; Rasband, Wayne S.; Eliceiri, Kevin W. Nature Methods, Vol. 9, Issue 7 https://doi.org/10.1038/nmeth.2089	journal	June 2012
Restructuring in high burn-up pressurized water reactor UO₂ fuel central parts: Experimental 3D characterization by focused ion beam—scanning electron microscopy Noirot, Jean; Dowek, Rébecca; Zacharie-Aubrun, Isabelle Journal of Applied Physics, Vol. 132, Issue 19 https://doi.org/10.1063/5.0105072	journal	November 2022
A Threshold Selection Method from Gray-Level Histograms Otsu, Nobuyuki IEEE Transactions on Systems, Man, and Cybernetics, Vol. 9, Issue 1 https://doi.org/10.1109/TSMC.1979.4310076	journal	January 1979
REVIEW OF 15 YEARS OF HIGH-DENSITY LOW-ENRICHED UMo DISPERSION FUEL DEVELOPMENT FOR RESEARCH REACTORS IN EUROPE Van Den Berghe, S.; Lemoine, P. Nuclear Engineering and Technology, Vol. 46, Issue 2 https://doi.org/10.5516/NET.07.2014.703	journal	April 2014
IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL Meyer, M. K.; Gan, J.; Jue, J. F. Nuclear Engineering and Technology, Vol. 46, Issue 2 https://doi.org/10.5516/NET.07.2014.706	journal	April 2014

Similar Records

Microstructural characterization of as-fabricated and irradiated U-Mo fuel using SEM/EBSD

Journal Article · 2018 · Journal of Nuclear Materials · OSTI ID:1548124

Jadernas, Daniel; Gan, Jian; Keiser, Dennis; +4 more

High-energy synchrotron study of in-pile-irradiated U–Mo fuels

Journal Article · 2015 · Scripta Materialia · OSTI ID:1367858

Miao, Yinbin; Mo, Kun; Ye, Bei; +11 more

Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel

Journal Article · 2023 · Journal of Nuclear Materials · OSTI ID:2283651

Salvato, Daniele; Smith, Charlyne A.; Pavlov, Tsvetoslav R.; +19 more

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
25228
HEU
LEU
RERTR
U-Mo fuel
USHPRR
fission gas bubbles
image analysis
porosity analysis
scanning electron microscopy

Title: Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel

Citation Formats

References (37)

Similar Records

Related Subjects