• 文献标题:   Pool boiling CHF enhancement by graphene-oxide nanofluid under nuclear coolant chemical environments
  • 文献类型:   Article
  • 作  者:   PARK SD, LEE SW, KANG S, KIM SM, BANG IC
  • 作者关键词:  
  • 出版物名称:   NUCLEAR ENGINEERING DESIGN
  • ISSN:   0029-5493 EI 1872-759X
  • 通讯作者地址:   UNIST
  • 被引频次:   40
  • DOI:   10.1016/j.nucengdes.2012.07.016
  • 出版年:   2012

▎ 摘  要

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. (C) 2012 Elsevier B.V. All rights reserved.