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Abstrakty
Fluids at supercritical pressures are considered to be very promising as coolants for Generation IV reactor systems, including the supercritical water cooled reactor (SCWR), the CO2-cooled reactor (SCCO2R) and the Brayton cycle as a secondary system in sodium-cooled fast reactors. The operating conditions of such reactors allow for a significant thermodynamic efficiency increase of the respective power plants. On the other hand, several unresolved issues must still be addressed in order to develop a viable design of supercritical fluid nuclear systems. Examples include: in-core heat transfer in SCWRs, heat exchangers in the S-CO2 Brayton cycle, and flows in complex geometries of SCO2 compressors. It has been shown before that the understanding of the effect of fluid property variations on turbulence is a major factor in our ability to predict the combined fluid mechanics and heat convection in systems and components using supercritical fluids. The objective of this paper is to present the results of analysis on the effect of local multidimensional flow and heat transfer phenomena on the temperature distribution inside future SCWRs. Two proposed SCWR designs have been considered: a single-pass and a two-pass coolant flow configurations through the reactor core. It should be noted that a preliminary documentation of the results of the current work has been included in the materials of the NURETH-15 conference.
Czasopismo
Rocznik
Tom
Strony
51--60
Opis fizyczny
Bibliogr. 10 poz., rys., tab., wykr.
Twórcy
autor
- Center for Multiphase Research, Rensselaer Polytechnic Institute, USA
autor
- Center for Multiphase Research, Rensselaer Polytechnic Institute, USA
autor
- Center for Multiphase Research, Rensselaer Polytechnic Institute, USA
Bibliografia
- [1] P. MacDonald, J. Buongiorno, J. W. Sterbentz, C. Davis, R. Witt, Feasibility study of supercritical water cooled reactors for electric power production, Final Report INEEL/EXT-04-02530, Idaho National Laboratory (INL) (2005).
- [2] Y. Oka, S. Koshizuka, T. Yamasaki, Direct cycle light water reactor operating at supercritical pressure, J. Nucl. Sci. Technol 29 (1992) 585–588.
- [3] J. Licht, M. Anderson, M. Corradini, Heat transfer to water at supercritical pressures in a circular and square annular flow geometry, Int. J. Heat Fluid Flow 29 (2008) 156–166. doi:10.1016/j.ijheatfluidflow.2007.09.007.
- [4] H. Anglart, T. Gallaway, S. P. Antal, M. Z. Podowski, Prediction and analysis of onset of turbulent convective heat transfer deterioration in supercritical water flows, in: Proc. ICAPP 7, 2007.
- [5] K. Yamagata, K. Nishikawa, S. Hasegawa, T. Fujii, S. Yoshida, Forced convective heat transfer to supercritical water flowing in tubes, Int. J. Heat Mass Transfer 15 (1972) 2575–2593.
- [6] T. Gallaway, S. P. Antal, M. Z. Podowski, Multidimensional model of fluid flow and heat transfer in generationiv supercritical water reactors, Nucl. Eng. Des. 238 (2008) 1909–1916.
- [7] T. Gallaway, S. Antal, M. Z. Podowski, On the multidimensional modeling of fluid flow and heat transfer in scwrs, in: Proc. ICAPP’12, 2012, pp. 231–239.
- [8] S. P. Antal, NPHASE-CMFD User Manual, Interphase Dynamics, LLC (2011).
- [9] H. Kim, Y. Y. Bae, H. Y. Kim, J. H. Song, B. H. Cho, Experimental investigation on the heat transfer characteristics in a vertical upward flow of supercritical co2, in: Proc. of ICAPP, 2006.
- [10] M. Z. Podowski, Thermal-hydraulic aspects of scwr design, Journal of Power and Energy Systems 2 (1) (2008) 352–360.
Typ dokumentu
Bibliografia
Identyfikator YADDA
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