journal article·2022-08Open access

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

J Fay, F. Di Lemma, A. Gribok, K. Paaren, P. Medvedev, L. Capriotti, D. Porter, J. Lian

Abstract

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. 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.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (21)

Show source-provided references
1. A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents10.1016/j.net.2015.03.004 ↗
2. Metallic fuels for advanced reactors10.1016/j.jnucmat.2009.03.007 ↗
3. Characterization of a minor actinides bearing metallic fuel pin irradiated in EBR-II10.1016/j.jnucmat.2020.152279 ↗
4. 3.23 - metal fuel performance modeling and simulation
5. Performance of low smeared density sodium-cooled fast reactor metal fuel10.1016/j.jnucmat.2015.06.014 ↗
6. Investigation of fuel microstructure at the top of a metallic fuel pin after a reactor overpower transient10.1016/j.jnucmat.2020.152711 ↗
7. Metallic fast reactor fuels10.1016/0149-1970(96)00005-4 ↗
8. Kinetics of fission-gas-bubble-nucleated void swelling of the alpha-uranium phase of irradiated U-Zr and U-Pu-Zr fuel10.1016/0022-3115(93)90261-V ↗
9. Pahl · 1990
10. Initial demonstration of automated fuel performance modeling with 1977 EBR-II metallic fuel pins using BISON code with FIPD and IMIS databases10.1016/j.nucengdes.2021.111393 ↗
11. FIPD: The SFR metallic fuels irradiation & physics database10.1016/j.nucengdes.2021.111225 ↗
12. NIH Image to ImageJ: 25 years of image analysis10.1038/nmeth.2089 ↗
13. R.G. Pahl, C.E. Lahm, R. Villarreal, G.L. Hofman, W.N. (1986). Recent irradiation tests of uraniumplutonium-zirconium metal fuel elements (CONF-860931–9). United States.
14. Experience with advanced driver fuels in EBR-II10.1016/0022-3115(93)90207-F ↗
15. Performance of HT9 clad metallic fuel at high temperature10.1016/0022-3115(93)90210-P ↗
16. J. Watkins, An introduction to the science of statistics: from theory to implimentation, 2016. ISBN N/A Publication date:16 Feb 2016 avaialable online https://www.freetechbooks.com/an-introduction-to-the-science-of-statistics-from-theory-toimplementation-preliminary-edition-t1277.html.
17. Statsmodels: econometric and statistical modeling with python10.25080/Majora-92bf1922-011 ↗
18. Scikit-learn: machine learning in python
19. Extended fuel swelling models and ultra high burn-up fuel behavior of U–Pu–Zr metallic fuel using FEAST-METAL10.1016/j.nucengdes.2013.02.004 ↗
20. Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: a critical review
21. Experimental system for studying temperature gradient-driven fracture of oxide nuclear fuel out of reactor10.1063/1.5119361 ↗