File Download

There are no files associated with this item.

  • Find it @ UNIST can give you direct access to the published full text of this article. (UNISTARs only)
Related Researcher

방인철

Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
Read More

Views & Downloads

Detailed Information

Cited time in webofscience Cited time in scopus
Metadata Downloads

Full metadata record

DC Field Value Language
dc.citation.conferencePlace US -
dc.citation.conferencePlace Chicago -
dc.citation.endPage 1896 -
dc.citation.startPage 1890 -
dc.citation.title International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 -
dc.citation.volume 3 -
dc.contributor.author Park, SD -
dc.contributor.author Lee, SW -
dc.contributor.author Kang, S -
dc.contributor.author Kim, SM -
dc.contributor.author Seo, H -
dc.contributor.author Bang, In Cheol -
dc.date.accessioned 2023-12-20T02:06:44Z -
dc.date.available 2023-12-20T02:06:44Z -
dc.date.created 2013-06-10 -
dc.date.issued 2012-06-24 -
dc.description.abstract External reactor vessel cooling (ERVC) for in-vessel retention (IVR) of corium as a key severe accident management strategy can be achieved by flooding the reactor cavity during a severe accident. In this accident mitigation strategy, the decay heat removal capability depends on whether the imposed heat flux exceeds critical heat flux (CHF). To provide sufficient cooling for high-power reactors such as APR1400, there have been some R&D efforts to use the reactor vessel with micro-porous coating and nanofluids boiling-induced coating. The dispersion stability of graphene-oxide nanofluid in the chemical conditions of flooding water that includes boric acid, lithium hydroxide (LiOH) and tri-sodium phosphate (TSP) was checked in terms of surface charge or zeta potential before the CHF experiments. Results showed that graphene-oxide nanofluids were very stable under ERVC environment. The critical heat flux (CHF) on the reactor vessel external wall was measured using the small scale two-dimensional slide test section. The radius of the curvature is 0.1m. The dimension of each part in the facility simulated the APR-1400. The heater was designed to produce the different heat flux. The magnitude of heat flux follows the one of the APR-1400 when the severe accident occurred. All tests were conducted under inlet subcooling 10K. Graphene-oxide nanofluids (concentration : 10 -4 V%) enhanced CHF limits up to about 20% at mass flux 50kg/m2s and 100kg/m2s in comparison with the results of the distilled water at same test condition. -
dc.identifier.bibliographicCitation International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, v.3, pp.1890 - 1896 -
dc.identifier.isbn 978-162276210-1 -
dc.identifier.scopusid 2-s2.0-84869017396 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/43030 -
dc.language 영어 -
dc.publisher International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 -
dc.title An experimental study of external reactor vessel cooling strategy on the critical heat flux using the graphene oxide nanofluid -
dc.type Conference Paper -
dc.date.conferenceDate 2012-06-24 -

qrcode

Items in Repository are protected by copyright, with all rights reserved, unless otherwise indicated.