Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation

Ye, B.; Miao, Y.; Shi, J.; Salvato, D.; Mo, K.; Jamison, L.; Bergeron, A.; Hofman, G. L.; Leenaers, A.; Oaks, A.; Yacout, A. M.; Van den Berghe, S.; Petry, W.; Kim, Y. S.

doi:10.1016/j.jnucmat.2020.152684

Title: Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation

Journal Article · Thu Nov 19 00:00:00 EST 2020 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2020.152684· OSTI ID:1776841

Ye, B. ^[1];

^[1]; Shi, J. ^[2]; Salvato, D. ^[3]; Mo, K. ^[1]; Jamison, L. ^[1]; Bergeron, A. ^[1]; Hofman, G. L. ^[1]; Leenaers, A. ^[4]; Oaks, A. ^[1]; Yacout, A. M. ^[1]; Van den Berghe, S. ^[3]; Petry, W. ^[2]; Kim, Y. S. ^[1]

Argonne National Lab. (ANL), Lemont, IL (United States)
Technische Univ. Munchen, Garching (Germany). Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II)
Nuclear Material Science Institute, SCK CEN, Mol (Belgium); Ghent Univ., Ghent (Belgium)
Nuclear Material Science Institute, SCK CEN, Mol (Belgium)

A high-energy Xe ion irradiation experiment was conducted to investigate the temperature dependence of interdiffusion in bilayer Al-UMo samples under irradiation. The amount of interdiffusion achieved at a fixed dose with the increase of temperature showed a clear transition at 175 degrees C (with an estimated error in the range of ± 10 degrees C) from temperature-independent to temperature-dependent behavior. The activation energy derived from the curve of interdiffusion quantity vs. irradiation temperature is 0.77 ± 0.16 eV. This information has been utilized to understand the temperature effect on the interdiffusion process that occurred at the interfaces of U-Mo particles and the Al matrix in U-Mo/Al dispersion fuels, whose magnitude significantly impacts the fuel's performance. Although this temperature effect was deemed important, it cannot be examined directly using in-pile irradiation data, as fuel temperatures cannot be measured in reactor irradiation and are highly correlated with fission rate and thermal conductivity evolution. To connect the knowledge accumulated from ion irradiation with in-pile irradiation data, simulation of a full-sized U-Mo/Al dispersion fuel plate irradiated in the FUTURE test in the BR2 reactor was performed with the Dispersion Analysis Research Tool (DART), a dispersion fuel performance code. DART is equipped with an interaction or interdiffusion layer (IL) growth correlation formulated to describe the temperature dependence of ion mixing results. The agreement between calculated and measured fuel meat constituent volume fractions and swelling data demonstrated that the temperature effect on in-pile Al-UMo interdiffusion is well captured with the correlation. In this case, the fitted activation energy is 0.70 eV. Considering the uncertainties associated with the ion irradiation data, the activation energy obtained from in-pile data fitting is in accord with that from ion irradiation results.

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

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation; USDOE Office of Nuclear Energy (NE); Bundesministerium für Bildung und Forschung (BMBF)

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 1776841

Alternate ID(s):: OSTI ID: 1776054

Journal Information:: Journal of Nuclear Materials, Vol. 544; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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heavy ion irradiation
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