An analysis of fluff formation in metallic fuel via data analyzes from EBR-II experiments and BISON fuel code modeling

Fay, Jake; Di Lemma, Fidelma Giulia; Gribok, Andrei V.; Paaren, Kyle Mitchell; Medvedev, Pavel G.; Capriotti, Luca; Porter, Douglas L.; Lian, J.

doi:10.1016/j.jnucmat.2022.153813

An analysis of fluff formation in metallic fuel via data analyzes from EBR-II experiments and BISON fuel code modeling

Journal Article · Wed May 25 00:00:00 EDT 2022 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2022.153813· OSTI ID:1902904

^[1]; ^[2]; ^[2]; Paaren, Kyle Mitchell ^[2]; ^[2]; ^[2]; ^[2]; Lian, J. ^[1]

Rensselaer Polytechnic Inst., Troy, NY (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

During the operation of EBR-II, it was found that a highly porous structure (over 40% area fraction) formed at the top of several fuel columns. Previous work has shown that this structure, designated fluff in this paper, contains a significant fraction of fuel elements (e.g., U and Pu) which could potentially impact neutronics. This work aims in analyzing the formation mechanism of this microstructure so its impact can be incorporated into future metallic fuel modeling codes and algorithms. This paper details a preliminary examination into the formation mechanisms of fluff by performing qualitative and statistical analysis of EBR-II experimental data. Additionally, the operating conditions that have the greatest impact on fluff formation were determined based on this data set. Also, BISON fuel code simulations were used to help postulate potential fluff formation mechanisms. From this analysis it was found that the largest contributors to fluff formation were fuel burnup and composition, with fluff formation exhibiting a roughly linear positive correlation with increasing burnup and a negative correlation with increasing Pu content. It was also found that higher pin operating temperatures decreased fluff formation but only for U-10Zr fuels.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1902904

Report Number(s):: INL/JOU-21-65251-Rev000

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 567; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (15)

Experience with advanced driver fuels in EBR-II Lahm, C. E.; Koenig, J. F.; Pahl, R. G. Journal of Nuclear Materials, Vol. 204 https://doi.org/10.1016/0022-3115(93)90207-F	journal	September 1993
Performance of HT9 clad metallic fuel at high temperature Pahl, R. G.; Lahm, C. E.; Hayes, S. L. Journal of Nuclear Materials, Vol. 204 https://doi.org/10.1016/0022-3115(93)90210-P	journal	September 1993
Kinetics of fission-gas-bubble-nucleated void swelling of the alpha-uranium phase of irradiated U-Zr and U-Pu-Zr fuel Rest, J. Journal of Nuclear Materials, Vol. 207 https://doi.org/10.1016/0022-3115(93)90261-V	journal	December 1993
Metallic fast reactor fuels Hofman, G. L.; Walters, L. C.; Bauer, T. H. Progress in Nuclear Energy, Vol. 31, Issue 1-2 https://doi.org/10.1016/0149-1970(96)00005-4	journal	January 1997
Metallic fuels for advanced reactors Carmack, W. J.; Porter, D. L.; Chang, Y. I. Journal of Nuclear Materials, Vol. 392, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.03.007	journal	July 2009
Performance of low smeared density sodium-cooled fast reactor metal fuel Porter, D. L.; Chichester, H. J. M.; Medvedev, P. G. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.014	journal	October 2015
Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II Capriotti, Luca; Harp, Jason M. Journal of Nuclear Materials, Vol. 539 https://doi.org/10.1016/j.jnucmat.2020.152279	journal	October 2020
Investigation of fuel microstructure at the top of a metallic fuel pin after a reactor overpower transient Di Lemma, Fidelma G.; Wright, Karen E.; Capriotti, Luca Journal of Nuclear Materials, Vol. 544 https://doi.org/10.1016/j.jnucmat.2020.152711	journal	February 2021
A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents Sofu, Tanju Nuclear Engineering and Technology, Vol. 47, Issue 3 https://doi.org/10.1016/j.net.2015.03.004	journal	April 2015
Extended fuel swelling models and ultra high burn-up fuel behavior of U–Pu–Zr metallic fuel using FEAST-METAL Karahan, Aydın; Andrews, Nathan C. Nuclear Engineering and Design, Vol. 258 https://doi.org/10.1016/j.nucengdes.2013.02.004	journal	May 2013
FIPD: The SFR metallic fuels irradiation & physics database Yacout, Abdellatif M.; Mo, Kun; Oaks, Aaron Nuclear Engineering and Design, Vol. 380 https://doi.org/10.1016/j.nucengdes.2021.111225	journal	August 2021
Initial demonstration of automated fuel performance modeling with 1977 EBR-II metallic fuel pins using BISON code with FIPD and IMIS databases Paaren, Kyle M.; Gale, Micah; Kerr, Matthew J. Nuclear Engineering and Design, Vol. 382 https://doi.org/10.1016/j.nucengdes.2021.111393	journal	October 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
Experimental system for studying temperature gradient-driven fracture of oxide nuclear fuel out of reactor Patnaik, S.; Lopes, D. A.; Besmann, T. M. Review of Scientific Instruments, Vol. 91, Issue 3 https://doi.org/10.1063/1.5119361	journal	March 2020
Statsmodels: Econometric and Statistical Modeling with Python Seabold, Skipper; Perktold, Josef Proceedings of the Python in Science Conference https://doi.org/10.25080/Majora-92bf1922-011	conference	January 2010

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