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Article

Thermal hydraulic analysis of supercritical water reactor cooled by TiO2 nanofluid

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Pages 291-299 | Received 02 Oct 2018, Accepted 11 Jan 2019, Published online: 03 Feb 2019

References

  • Gupta HK, Agrawal GD, Mathur J. An overview of nanofluids: A new media towards green environment. Int J Envi Sci. 2012;3(1):433–440.
  • Yang Y, Zhang ZG, Grulke EA, et al. Heat transfer properties of nanoparticle-in-fluid dispersions nanofluids in laminar flow. Int J Heat Mass Transfer. 2012;48(6):1107–1116.
  • Wang X, Xu X, Choi SUS. Thermal conductivity of nanoparticles-fluid mixture. J Thermophys Heat Transfer. 1999;13(4):474–480.
  • Ebrahimian M, Ansarifar. GR. Investigation of the nano fluid effects on heat transfer characteristics in nuclear reactors with dual cooled annular fuel using CFD (Computational Fluid Dynamics) modeling. Energy. 2016;98:1–14.
  • Ramadham AI, Ery Diniardi R. Effect analysis of volume fraction of nanofluid Al2O3-water on natural convection heat transfer coefficient in small modular reactor. World J Nucl Sci Technol. 2016;6:79–88.
  • Bahrevar MH, Jahanfarnia G, Pazirandeh A, et al. Thermal-hydraulic analysis of a novel design super critical water reactor with Al2O3 nanofluid as a coolant. J Supercrit Fluids. 2018;140:41–52.
  • Liu XJ, Yang T, Cheng X. Development and assessment of a sub-channel code applicable for trans-critical transient of SCWR. Nucl Eng Des. 2013;262:499–509.
  • Nourollahi R, Esteki MH, Jahanfamia. G. Thermal-hydraulic noise analysis of a VVER-1000 reactor with nanofluid as coolant. Prog Nucl Energy. 2018;108:334–350.
  • Pioro IL, Duffey RB. Heat transfer and hydraulic resistance at supercritical pressures in power engineering applications. New York (NY): ASME Press; 2007. p. 334.
  • Dyadyakin BV, Popov AS. Heat transfer and thermal resistance of tight seven-rod bundle, cooled with water flow at supercritical pressures. Trans VTI. 1977;11:244–253.
  • Mokry S. Development of a heat transfer correlation for supercritical water in supercritical water-cooled reactor applications. Oshawa, Canada: UOIT; 2009.
  • McAdams WH. Heat transmission. 2nd ed. New York (NY): McGraw-Hill Book Company; 1942.
  • Wang H, Wang W, Qincheng Bi and Linchuan Wang. Experimental study of heat transfer and flow resistance of supercritical pressure water in a SCWR sub-channel. J Supercrit Fluids. 2015;100:15–25.
  • Grande LC. Thermal aspect of using alternative nuclear fuels in supercritical water cooled reactors. Ontario: University of Ontario Institute of Technology; 2010.
  • Grande L, Peiman W, Villamere B, et al. Thermal aspects of alternative fuels for use in supercritical water-cooled nuclear reactors. Proceedings of the 11th International Conference on CANDU Fuel, Niagra Falls, Ontario.
  • Samuel J. Conceptual design for a re-entrant type fuel channel for supercritical water-cooled nuclear reactors. Ontario: University of Ontario Institute of Technology; 2011.
  • Velagapudi V, Konijeti RK, Aduru CSK. Empirical correlations to predict thermophysical and heat transfer characteristics of nanofluids. Therm Sci. 2008;12:27–37.
  • Suriyawong A, Dalkilic AS, Wongwises S. Nucleate pool boiling heat transfer correlation for TiO2-water nanofluids. J ASTM Int. 2012;9(5):1–12.
  • Rahimi MH, Jahanfarnia G, Vosoughi N. Thermal-hydraulic analysis of nanofluids as the coolant in supercritical water reactors. J Supercrit Fluids. 2017;128:47–56.
  • Muftah FB, Bede G. A simple computer programmed for the calculations of reactor channel temperature distribution. Budapest: Department of energy Technical University Budapest; 1997. p. 133–142.
  • Samuel J, Harvel G, Pioro I. Heat loss analysis of a re-entrant fuel channel for SCWR type reactors. (ISSCWR-5), 5th International Conference Symposium on Supercritical Water-Cooled Reactors; 2011 Mar 13–16; Canada.
  • Oka Y, Koshizuka S. Supercritical-pressure, once-through cycle light water cooled reactor concept. J Nucl Sci Technol. 2001;38(12).
  • Pioro IL, Khartabil HF, Duffey RB. Heat transfer to supercritical fluids flowing in channels—empirical correlations (survey). Nucl Eng Des. 2004;230:69–91.
  • Zarifi E, Jahanfarnia G, Veysi F. Thermal–hydraulic modeling of nanofluids as the coolant in VVER-1000 reactor core by the porous media approach. Ann Nucl Energy. 2013;51:203–212.

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