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Article

Evaluation of nanofluids for enhancing critical heat flux for in-vessel retention during sever reactor accidents

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Pages 499-509 | Received 18 Mar 2021, Accepted 14 Sep 2021, Published online: 25 Oct 2021

References

  • Rempe JL, Suh KY, Cheung FB, et al. In-vessel retention strategy for high power reactors final report. Idaho Falls (ID): Idaho National Engineering and Environmental Laboratory, Bechtel BWXT Idaho, LLC; 2005. (INEEL/EXT–04–02561).
  • Theofanous TG, Liu C, Additon S, et al. In-vessel coolability and retention of a core melt. Washington (DC): US Department of Energy; 1996. (DOE/ID–10460).
  • Theofanous TG, Tu JP, Salmassi T, et al. Quantification of limit to coolability in ULPU-2000 configuration IV. Santa Barbara (CA): University of California Center for Risk Studies and Safety; 2002. (CRSS Technical Report 02.05.3).
  • Dinh TN, Tu JP, Salmassi T, et al. Limit of coolability in the AP1000-related ULPU-2400 configuration V facility. Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics; 2003 Oct 5–9; Seoul, Korea. Taejon (Korea): Korea Nuclear Society.
  • Rougé S. SULTAN test facility for large-scale vessel coolability in natural convection at low pressure. Nucl Eng Des. 1997;169(1–3):185–195.
  • Rougé S, Dor I, Geffraye G. Reactor vessel external cooling for corium retention SULTAN experimental program and modeling with CATHARE code. Workshop on In-vessel Core Debris Retention and Coolability; 1998 Mar 3–6; Garching, Germany. Paris (France): Nuclear Energy Agency; 1999. p. 351–363.
  • Aoki K, Iwaki C, Sato H, et al. Testing plan for critical heat flux measurement during in-vessel retention. Proceedings of the 23rd International Conference on Nuclear Engineering; 2015 May 17–21; Chiba, Japan. Tokyo (Japan): Japan Society of Mechanical Engineers. (Paper 1088).
  • Aoki K, Iwaki C, Sato H, et al. Critical heat flux measurement during in-vessel retention. Proceedings of the 2015 Japan-U.S. Seminar on Two-phase Flow Dynamics; 2015 May 10–16; West Lafayette (IN).
  • Iwaki C, Sato H, Kanamori D. Development of critical heat flux correlation for in-vessel retention. J Nucl Sci Technol. 2020;57(8):951–962.
  • You SM, Kim JH, Kim KH. Effect of nanoparticles on critical heat flux of water in pool boiling heat transfer. Appl Phys Lett. 2003;83(16):3374–3376.
  • Vassal P, Kumarb R, D’Amicoa S. Pool boiling heat transfer experiments in silica–water nano-fluids. Int J Heat Mass Transf. 2004;47(2):407–411.
  • Kim SJ, Bang IC, Buongiorno J, et al. Surface wettability change during pool boiling of nanofluids and its effect on critical heat flux. Int J Heat Mass Transf. 2007;50(19–20):4105–4116.
  • Kim SJ, McKrell T, Buongiorno J, et al. Experimental study of flow critical heat flux in alumina-water, zinc-oxide-water and diamond-water nanofluids. J Heat Transf. 2009;131(4):1–7.
  • Ahn HS, Kim H, Jo H, et al. Experimental study of critical heat flux enhancement during forced convective flow boiling of nanofluid on a short heated surface. Int J Multiph Flow. 2010;36(5):375–384.
  • DeWitt G, McKrell T, Buongiorno J, et al. Experimental study of critical heat flux with alumina-water nanofluids in downward-facing channels for in-vessel retention applications. Nucl Eng Tech. 2013;45(3):335–346.
  • Celata GP, Cumo M, Mariani A, et al. Rationalization of existing mechanistic models for the prediction of water subcooled flow boiling critical heat flux. Int J Heat Mass Transf. 1994;37(Suppl 1):347–360.
  • Park SD, Moon SB, Bang IC. Study on nanoparticle coating thickness on critical heat flux in pool boiling heat transfer. Proceedings of the 2013 International Congress on Advances in Nuclear Power Plants; 2013 Apr 14–18; Jeju Island, Korea. Daejeon (Korea): Korean Nuclear Society; 2014.

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