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.