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Author

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

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Flow boiling CHF enhancement in an external reactor vessel cooling (ERVC) channel using graphene oxide nanofluid

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Title
Flow boiling CHF enhancement in an external reactor vessel cooling (ERVC) channel using graphene oxide nanofluid
Author
Park, Seong DaeBang, In Cheol
Keywords
CRITICAL HEAT-FLUX; SIC NANOFLUIDS; POOL; RETENTION; SURFACE; COOLABILITY; PRESSURE; CORIUM
Issue Date
201312
Publisher
ELSEVIER SCIENCE SA
Citation
NUCLEAR ENGINEERING AND DESIGN, v.265, no., 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.
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DOI
http://dx.doi.org/10.1016/j.nucengdes.2013.08.064
ISSN
0029-5493
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