Aluminum cladding oxide growth prediction for high flux research reactors

Kim, Yeon Soo; Chae, H. T.; Van den Berghe, S.; Leenaers, A.; Kuzminov, V.; Yacout, A. M.

doi:10.1016/j.jnucmat.2019.151926

Aluminum cladding oxide growth prediction for high flux research reactors

Journal Article · Sun Nov 24 00:00:00 EST 2019 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2019.151926· OSTI ID:1606400

Kim, Yeon Soo ^[1]; Chae, H. T. ^[2]; Van den Berghe, S. ^[3]; Leenaers, A. ^[3]; Kuzminov, V. ^[3]; Yacout, A. M. ^[1]

Argonne National Lab. (ANL), Argonne, IL (United States)
Korea Atomic Energy Research Inst. (KAERI), Daejeon (South Korea)
SCK.CEN, Mol (Belgium)

Aluminum cladding oxidation of research-reactor fuel elements at high power conditions has a disadvantageous effect on fuel performance due to the lower thermal conductivity of the oxide. The oxide growth prediction models available in the literature were mostly developed for low power conditions. To examine the applicability of the models to high power and high temperature test conditions, the models were studied by coupling with the most frequently employed heat transfer coefficient (HTC) correlations including the Dittus-Boelter correlation, the Colburn correlation, the Sieder-Tate correlation, and KAERI-developed correlation. The Griess model over-predicted the oxide growth while the KAERI-Griess model under-predicted the oxide growth for high power tests. The Kim model, coupled with the Colburn correlation, gave most consistent results with the measured data from two BR2 experiments. However, the Kim model was found to be inapplicable to the EUHFRR conditions at the peak power locations if it was coupled with the Dittus-Boelter correlation. A revision of the prediction models to more closely agree with the measured data was recommended. Furthermore, AG3NE and AlFeNi cladding types were tested in the E-FUTURE experiment, and a noticeable (although small) reduction in oxide thickness on the AlFeNi cladding was observed. However, this difference was believed to be only a secondary effect considering other uncertainties in model predictions, so no attempt was made to model the alloying effect.

Research Organization:: Argonne National Laboratory (ANL), Argonne, IL (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 1606400

Alternate ID(s):: OSTI ID: 1580774

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 529; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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