Pool boiling CHF enhancement by micro/nanoscale modification of zircaloy-4 surface
SCIE
SCOPUS
- Title
- Pool boiling CHF enhancement by micro/nanoscale modification of zircaloy-4 surface
- Authors
- Ho Seon Ahn; Chan Lee; Hyungdae Kim; HangJin Jo; SoonHo Kang; Kim, J; Jeongseob Shin; KIM, MOO HWAN
- Date Issued
- 2010-10
- Publisher
- ELSEVIER SCIENCE SA
- Abstract
- Consideration of the critical heat flux (CHF) requires difficult compromises between economy and safety in many types of thermal systems, including nuclear power plants. Much research has been directed towards enhancing the CHF, and many recent studies have revealed that the significant CHF enhancement in nanofluids is due to surface deposition of nanoparticles. The surface deposition of nanoparticles influenced various surface characteristics. This fact indicated that the surface wettability is a key parameter for CHF enhancement and so is the surface morphology. In this study, surface wettability of zircaloy-4 used as cladding material of fuel rods in nuclear power plants was modified using surface treatment technique (i.e. anodization). Pool boiling experiments of distilled water on the prepared surfaces was conducted at atmospheric and saturated conditions to examine effects of the surface modification on CHF. The experimental results showed that CHF of zircaloy-4 can be significantly enhanced by the improvement in surface wettability using the surface modification, but only the wettability effect cannot explain the CHF increase on the treated zircaloy-4 surfaces completely. It was found that below a critical value of contact angle (10 degrees), micro/nanostructures created by the surface treatment increased spreadability of liquid on the surface, which could lead to further increase in CHF even beyond the prediction caused only by the wettability improvement. These micro/nanostructures with multiscale on heated surface induced more significant CHF enhancement than it based on the wettability effect, due to liquid spreadability. (C) 2010 Elsevier B.V. All rights reserved.
- URI
- https://oasis.postech.ac.kr/handle/2014.oak/30785
- DOI
- 10.1016/J.NUCENGDES.2010.07.006
- ISSN
- 0029-5493
- Article Type
- Article
- Citation
- NUCLEAR ENGINEERING AND DESIGN, vol. 240, no. 10, page. 3350 - 3360, 2010-10
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