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.
Authors
- Yidan Yuan (ORCID: https://orcid.org/0000-0002-4418-4396)
- Weimin Ma (ORCID: https://orcid.org/0000-0002-8917-7720)
- Erhui Chen
- Zhehao Qu (ORCID: https://orcid.org/0000-0001-6902-9176)
- Xuan Wang (ORCID: https://orcid.org/0000-0003-2485-7095)
- Yaopeng Gong
- Shanfang Huang (ORCID: https://orcid.org/0000-0002-4324-8642)
- Li Zhang (ORCID: https://orcid.org/0000-0001-9807-7804)
- Yin Bangyue
- Chuanjun Li (ORCID: https://orcid.org/0000-0002-3505-0679)
- Jingru Ren (ORCID: https://orcid.org/0009-0005-2001-9096)
Institutions
- China Institute of Atomic Energy (CN)
- China General Nuclear Power Corporation (China) (CN)
- KTH Royal Institute of Technology (SE)
- Tsinghua University (CN)
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