Thermophysical properties of UO2-ZrO2 melt measured by aerodynamic levitation

This study addresses the measurement of thermophysical properties in molten core materials (corium), which is crucial for modeling severe accidents in light water reactors. Due to the measurement challenges at temperatures above 3000 K, there is a significant lack of experimental data for corium. Focusing on a UO 2 -ZrO 2 melt (atomic ratio U/Zr=0.456), density and viscosity measurements were conducted using aerodynamic levitation, a non-contact method chosen to avoid interactions between the samples and container walls. Samples were prepared using the pressing sintering method and levitated by argon gas above a conical converging-diverging nozzle. Density was measured using the cooling traces method under the axisymmetric ellipsoid hypothesis, while viscosity was measured by inducing damped oscillations which occurred when the levitated droplet was forced to oscillate around its resonant frequency through acoustic excitation, followed by the cessation of the acoustic excitation. The provided data and derived equations for the density and viscosity of the UO 2 -ZrO 2 melt contribute to enriching the thermophysical property database for materials in nuclear reactors.

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Publication Details

Journal
Journal of Nuclear Materials
Published
2024-08-23
DOI
https://doi.org/10.1016/j.jnucmat.2024.155356
Citations
2
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
0.23
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article

Thermophysical properties of UO2-ZrO2 melt measured by aerodynamic levitation

Yidan Yuan, Weimin Ma, Erhui Chen, Zhehao Qu et al.
2 citations
Journal of Nuclear Materials
Nuclear Materials and Properties
0.23
article

Thermophysical properties of UO2-ZrO2 melt measured by aerodynamic levitation

Yidan Yuan, Weimin Ma, Erhui Chen, Zhehao Qu, Xuan Wang, Yaopeng Gong, Shanfang Huang, Li Zhang, Yin Bangyue, Chuanjun Li, Jingru Ren
article en
2 citations

Abstract

This study addresses the measurement of thermophysical properties in molten core materials (corium), which is crucial for modeling severe accidents in light water reactors. Due to the measurement challenges at temperatures above 3000 K, there is a significant lack of experimental data for corium. Focusing on a UO 2 -ZrO 2 melt (atomic ratio U/Zr=0.456), density and viscosity measurements were conducted using aerodynamic levitation, a non-contact method chosen to avoid interactions between the samples and container walls. Samples were prepared using the pressing sintering method and levitated by argon gas above a conical converging-diverging nozzle. Density was measured using the cooling traces method under the axisymmetric ellipsoid hypothesis, while viscosity was measured by inducing damped oscillations which occurred when the levitated droplet was forced to oscillate around its resonant frequency through acoustic excitation, followed by the cessation of the acoustic excitation. The provided data and derived equations for the density and viscosity of the UO 2 -ZrO 2 melt contribute to enriching the thermophysical property database for materials in nuclear reactors.

Journal of Nuclear MaterialsVol. 602
China Institute of Atomic Energy (CN), China General Nuclear Power Corporation (China) (CN), KTH Royal Institute of Technology (SE), Tsinghua University (CN)
Openalex Percentile: Top 52%
Nuclear Materials and Properties
0.23
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Thermophysical properties of UO2-ZrO2 melt measured by aerodynamic levitation — Yidan Yuan, Weimin Ma, et al. · Journal of Nuclear Materials (2024) | TGRS Research Map | TGRS