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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 | - |
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