Abstract
Large scale computations are being carried out in nuclear engineering fields such as light water reactors, fast breeder reactors, high temperature gas-cooled reactors and nuclear fusion reactors. The computational fluid dynamics (CFD) regarding not only the single-phase flows but also the two-phase flow plays an important role for the developments of advanced nuclear reactor systems. In this review paper, some examples of large scale computations in nuclear engineering fields are illustrated by using a parallel visualization.
Key words
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Preview
Unable to display preview. Download preview PDF.
References
Kenning, D. B. R., Youyou, Y Pool boiling heat transfer on a thin plate: features revealed by liquid crystal thermography International Journal of Heat and Mass Transfer, Vol. 39, No. 15, 3117-3137, 1996.
Mikic, B. B., Rohsenow, W. M Bubble growth rates in non-uniform temperature field ASME J. Heat Transfer 91, 245-250, 1969.
Welch, S. W. J Local Simulation of Two-Phase Flows Including Interface Tracking with Mass Transfer J. Comput. Phys., vol. 121, 142-154, 1995.
Son, G., Dhir, V. K Numerical Simulation of Saturated Film Boiling on a Horizontal Surface J. Heat Transfer, Vol. 119, 525-533, 1997.
Juric, D., Tryggvason, G Computations of boiling flows Int. J. Multiphase Flow, vol. 24, 387-410, 1998.
Unverdi, S., Tryggvason, G A front-tracking method for viscous, incompressible, multifluid flows J. Comput. Phys., vol. 100, 25-37, 1992.
Kunugi, T MARS for Multiphase Calculation Computational Fluid Dynamics Journal, Vol.9, No. 1, 563-571, 2001
Carey, V. P Liquid-vapor Phase-change Phenomena - An introduction to the Thermophysics of Vaporization and Condensation Processes in Heat Transfer Equipment, Chapters 5 and 6, Taylor & Francis, 1992.
Brackbill, J. U., Kothe, D. B., Zemach, C A continuum method for modeling surface tension J. Comput. Phys., Vol. 100, 335-354, 1992.
Kunugi, T., Saito, N., Fujita, Y., Serizawa, A Direct Numerical Simulation of Pool and Forced Convective Flow Boiling Phenomena Heat Transfer 2002, Vol. 3, 497-502, 2002.
Kelly, J. E., Kao, S. P., Kazimi, M. S THERMIT-2: A two-fluid model for light water reactor subchannel transient analysis MIT-EL-81-014, 1981.
Thurgood, M. J COBRA/TRAC - A thermal-hydraulic code for transient analysis of nuclear reactor vessels and primary coolant systems, equation and constitutive models NURREG/CR-3046, PNL-4385, Vol. 1, R4, 1983.
Sugawara, S., Miyamoto, Y FIDAS: Detailed subchannel analysis code based on the three-fluid and threefield model Nuclear Engineering and Design, vol.129, 146-161, 1990.
Taylor, D TRAC-BD1/MOD1: An advanced best estimated computer program for boiling water reactor transient analysis, volume 1 - model description NUREG/CR-3633, 1984.
Liles, D TRAC-PF1/MOD1: An advanced best-estimate computer program for pressurized water reactor analysis NUREG/CR-3858, LA-10157-MS, 1986.
Iwamura, T., Okubo, T Development of reduced-moderation water reactor (RMWR) for sustainable energy supply Proc. 13th Pacific Basin Nuclear Conference (PBNC 2002), Shenzhen, China, 1631-1637, 2002.
Iwamura, T Core and system design of reduced-moderation water reactor with passive safety features Proc. 2002 International Congress on Advanced in Nuclear Power Plants (ICAPP 2002), No.1030, Hollywood, Florida, USA, 2002.
Okubo, T., Iwamura, T Design of small reduced-moderation water reactor (RMWR) with natural circulation cooling Proc. International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR2002), Seoul, Korea, 2002.
Earth Simulator Center, Annual report of the earth simulator center (April 2002- March 2003) Japan Marine Science and Technology Center, 2003.
Takase, K., Tamai, H., Yoshida, H., Akimoto, H Development of a Best Estimate Analysis Method on Two-Phase Flow Thermal-Hydraulics for Reduced-Moderation Water Reactors Proc. Best Estimate Twenty-O-Four (BE2004), Arlington, Washington D.C., USA, November, 2004.
Yoshida, H., Takase, K., Ose, Y., Tamai, H., Akimoto, H Numerical simulation of liquid film around grid spacer with interface tracking method Proc. International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), No.1111, Kyoto, Japan, 2003.
Takase, K., Yoshida, H., Ose, Y., Kureta, M., Tamai, H., Akimoto, H Numerical investigation of two-phase flow structure around fuel rods with spacers by large-scale simulations Proc. 5th International Conference on Multiphase Flow (ICMF04), No.373, Yokohama, Japan, June, 2004.
T. Yabe, T The constrained interpolation profile method for multiphase analysis J. computational Physics, vol.169, No.2, 556-593, 2001.
Youngs, D.L Numerical methods for fluid dynamics, Edited by Morton K.W. & Baine, M.J. Academic Press, 273-285, 1982.
Kureta, M., Liu, W., Tamai, H., Ohnuki, A., Mitsutake, T., Akimoto, H Development of Predictable Technology for Thermal/Hydraulic Performance of Reduced-Moderation Water Reactors (2) - Large-scale Thermal/Hydraulic Test and Model Experiments - Proc. 2004 International Congress on Advanced in Nuclear Power Plants (ICAPP 2002), No.4056, Pittsburg, Pennsylvania, USA, June, 2004.
Satake, S., Kunugi, T. Himeno, R High Reynolds Number Computation for Turbulent Heat Transfer in a Pipe Flow, M. Valero et al. (Eds.), Lecture Notes in Computer Science 1940 High Performance Computing, 514-523, 2000.
Satake, S., Kunugi, T., Takase, K., Ose, Y., Naito, N Large Scale Structures of Turbulent Shear Flow via DNS, A. Veidenbaum et al. (Eds.), Lecture Notes in Computer Science 2858 High Performance Computing, 468-475, 2003.
Satake, S., Kunugi, T., Takase, K., Ose, Y Direct numerical simulation of turbulent channel flow under a uniform magnetic field for large-scale structures at high Reynolds number Physics of Fluid, 18, 125106, 2006.
Author information
Authors and Affiliations
Corresponding author
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 2010 Springer Berlin Heidelberg
About this paper
Cite this paper
Kunugi, T., Satake, Si., Ose, Y., Yoshida, H., Takase, K. (2010). Large Scale Computations in Nuclear Engineering: CFD for Multiphase Flows and DNS for Turbulent Flows with/without Magnetic Field. In: Tromeur-Dervout, D., Brenner, G., Emerson, D., Erhel, J. (eds) Parallel Computational Fluid Dynamics 2008. Lecture Notes in Computational Science and Engineering, vol 74. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-14438-7_1
Download citation
DOI: https://doi.org/10.1007/978-3-642-14438-7_1
Published:
Publisher Name: Springer, Berlin, Heidelberg
Print ISBN: 978-3-642-14437-0
Online ISBN: 978-3-642-14438-7
eBook Packages: Mathematics and StatisticsMathematics and Statistics (R0)