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방인철

Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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Flow boiling CHF enhancement in an external reactor vessel cooling (ERVC) channel using graphene oxide nanofluid

Author(s)
Park, Seong DaeBang, In Cheol
Issued Date
2013-12
DOI
10.1016/j.nucengdes.2013.08.064
URI
https://scholarworks.unist.ac.kr/handle/201301/4233
Fulltext
http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=84886279143
Citation
NUCLEAR ENGINEERING AND DESIGN, v.265, pp.310 - 318
Abstract
External reactor vessel cooling for in-vessel retention of corium is an important concept to mitigate the consequences of a severe accident by flooding the reactor cavity. Although this system has some merits, it is restricted by the capacity of heat removal through the nucleate boiling on the outer surface of the reactor. In this study, the graphene oxide (GO) nanofluid at 0.0001 vol% was used to enhance the critical heat flux (CHF). The CHF tests were conducted with a closed-loop facility. Test section simulated the reactor vessel of APR-1400 with a small scale. The test results show about ∼20% enhancement of CHF at 50 and 100 kg/m2 s under a 10 K subcooling condition. It means that the additional thermal margin could be acquired by just adding the GO nanoparticles to the flooding water without severe economic concerns. It is also found that this CHF enhancement is caused by coating the graphene oxide nanoparticles on the heated surface. However, the sessile drop tests on the coated heater surface show that the wettability of GO coated surface is not improved. The results of IR thermography show that one of the promising reasons is the change of thermal activity due to the coated GO nanoparticles on the heated surface.
Publisher
ELSEVIER SCIENCE SA
ISSN
0029-5493

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