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DC Field | Value | Language |
---|---|---|
dc.citation.endPage | 191 | - |
dc.citation.startPage | 184 | - |
dc.citation.title | NUCLEAR ENGINEERING AND DESIGN | - |
dc.citation.volume | 252 | - |
dc.contributor.author | Park, Seong Dae | - |
dc.contributor.author | Lee, Seung Won | - |
dc.contributor.author | Kang, Sarah | - |
dc.contributor.author | Kim, Seong Man | - |
dc.contributor.author | Bang, In Cheol | - |
dc.date.accessioned | 2023-12-22T04:38:08Z | - |
dc.date.available | 2023-12-22T04:38:08Z | - |
dc.date.created | 2013-06-21 | - |
dc.date.issued | 2012-11 | - |
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. In present study, an experimental study has been conducted to investigate the viability of using graphene-oxide nanofluid under various coolant chemical environments to enhance CHF during ERVC. Pool boiling CHF experiments were carried out for the thin-wire heater with controlling the heater orientation from horizontal to vertical, or at 0 < theta < 90 degrees. The dispersion stability of graphene-oxide nanofluid in the chemical conditions of flooding water that includes boric acid, lithium hydroxide (DOH), and tri-sodium phosphate (TSP) was checked in terms of surface charge or zeta potential before the CHF experiments. Finally integral effects of graphene-oxide nanosheets and chemicals on CHF limits were investigated. Results showed that graphene-oxide nanofluids were very stable under ERVC coolant chemical environments and enhanced CHF limits up to about 40% at minimum at 90 degrees of angle (vertical orientation) and about 200% at maximum at 0 degrees of angle (horizontal orientation) in comparison to pure water. | - |
dc.identifier.bibliographicCitation | NUCLEAR ENGINEERING AND DESIGN, v.252, pp.184 - 191 | - |
dc.identifier.doi | 10.1016/j.nucengdes.2012.07.016 | - |
dc.identifier.issn | 0029-5493 | - |
dc.identifier.scopusid | 2-s2.0-84866715710 | - |
dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/3940 | - |
dc.identifier.url | http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=84866715710 | - |
dc.identifier.wosid | 000310040000021 | - |
dc.language | 영어 | - |
dc.publisher | ELSEVIER SCIENCE SA | - |
dc.title | Pool boiling CHF enhancement by graphene-oxide nanofluid under nuclear coolant chemical environments | - |
dc.type | Article | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.subject.keywordPlus | IN-VESSEL RETENTION | - |
dc.subject.keywordPlus | CRITICAL HEAT-FLUX | - |
dc.subject.keywordPlus | REACTORS | - |
dc.subject.keywordPlus | COOLABILITY | - |
dc.subject.keywordPlus | SURFACE | - |
dc.subject.keywordPlus | CORIUM | - |
dc.subject.keywordPlus | WATER | - |
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