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Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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Pool boiling critical heat flux behavior of cerium dioxide nanofluid under various volume concentration condition

Author(s)
Kim, J.Y.Bang, In Cheol
Issued Date
2019-05-19
URI
https://scholarworks.unist.ac.kr/handle/201301/79788
Citation
27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
Abstract
In this paper, the heat transfer behavior, especially about critical heat flux (CHF), of cerium dioxide (CeO2) is covered. The CeO2 which shows similar thermophysical properties such as thermal conductivity and diffusivity under 1000K are used as surrogate material to simulate the thermal performance of uranium dioxide (UO2) nanofluid inside the aqueous homogeneous reactor. All the wire pool boiling experiments are conducted under atmospheric condition. The CeO2 nanoparticles are used to make colloidal suspension of nanoparticles with the deionized (DI) water. The volume concentration from 0.0001 to 0.1 is made. To prevent the transient behavior of nanoparticles deposition on the heater surface during the boiling process of nanofluid, pre-nanoparticles deposited heater specimen are made for pool boiling experiment. The enhancement of the CHF value of CeO2 nanofluid is analyzed in the viewpoint of wettability change, an increased capillary force from porous layer formation by deposition of nanoparticles on the heater surface.
Publisher
American Society of Mechanical Engineers (ASME)

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