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Bang, In Cheol
Nuclear Thermal-Hydraulics & Reactor Safety Lab
Research Interests
  • Nuclear Thermal-Hydraulics

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Thermal-fluid characterizations of zno and sic nanofluids for advanced nuclear power plants

Cited 8 times inthomson ciCited 11 times inthomson ci
Title
Thermal-fluid characterizations of zno and sic nanofluids for advanced nuclear power plants
Author
Bang, In CheolKim, Ji Hyun
Keywords
Advanced nuclear power plants; Advanced reactors; Coating solution; Component materials; Critical Heat Flux; Diverse methods; Fluid characterization; Metal oxide nanoparticles; Nano-fluid; Nanofluids; Nuclear safety system; Preparation method; Primary systems; Promising materials; Radioactive cobalt; Thermal Performance; ZnO
Issue Date
201004
Publisher
AMER NUCLEAR SOC
Citation
NUCLEAR TECHNOLOGY, v.170, no.1, pp.16 - 27
Abstract
Nanofluids including metal or metal-oxide nanoparticles have shown improved thermal performance compared to water. Introducing zinc into a water-containing component of the primary system of a boiling water reactor or pressurized water reactor nuclear power plant is known to prevent the deposition of radioactive cobalt and to reduce the possible susceptibility of component materials to corrosion. Also, it is well known that silicon carbide (SiC) is a promising material for advanced reactors. Therefore, preparations of zinc oxide (ZnO) and SiC nanofluids have been used in diverse methods to reduce inconsistency of nanofluid performance. Thermal-fluid characterizations were carried out under the control of the preparation methods. In addition, indirect checks by contact angle measurements of depositions have shown that ZnO and SiC nanofluids as a self-recovering/healing coating solution can contribute to advanced nuclear safety systems in terms of the critical heat flux margin. The results show that more efforts are needed to develop the! nanofluid formulation to tailor the desired properties.
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ISSN
0029-5450
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