1. Development of analysis codes
H. Yoshida, H. Tamai, A. Ohnuki, K. Takase and H. Akimoto, Current Status of Thermal/Hydraulic Feasibility Project for Reduced-Moderation Water Reactor(2)-Development of Two-Phase Flow Simulation Code with Advanced Interface-Tracking Method-, Nuclear Engineering and Technology,38, 2, pp.119-128 (2006)
H. Yoshida and K. Takase, Numerical Evaluation of Fluid Mixing Phenomena in Boiling Water Reactor Using Advanced Interface Tracking Method, Journal of Fluid Science and Technology, 3, 2, pp.311-322 (2008)
H. Yoshida, T. Nagayoshi, K. Takase and H. Akimoto, Development of design technology on thermal-hydraulic performance in tight-lattice rod bundles: III- Numerical Evaluation of Fluid Mixing Phenomena using Advanced Interface-Tracking Method ?, Journal of Power and Energy Systems, 2, pp.250-261 (2008)
T. Misawa, H. Yoshida and H. Akimoto, Development of design technology on thermal-hydraulic performance in tight-lattice rod bundles: IV -Large Paralleled Simulation by the Advanced Two-fluid Model Code -, Journal of Power and Energy Systems, Vol.2, pp.262-270 (2008)
W. Zhang, H. Yoshida, Y. Ose, A. Ohnuki, H. Akimoto, A. Hotta and K. Fujimura, Numeral investigation of cross flow phenomena in a tight-lattice rod bundle using advanced interface tracking method, Journal of Power and Energy Systems, Vol.2 (2008) , pp.456-466
Conference:
H. Yoshida, A. Ohnuki, K. Takase, M. Kureta, H. Akimoto, et al, Development of Mechanistic Boiling Transition Model in Rod Bundles, Proc. Eleventh International Conference on Nuclear Engineering (ICONE11) (CD-ROM), ICONE11-36097 (2003)
H. Yoshida, Y. Ose, H. Tamai, K. Takase and H. Akimoto, 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) (CD-ROM), 1111 (2003)
H. Yoshida, K. Takase, Y. Ose, H. Tamai and H. Akimoto, Direct Numerical Simulation on Fluid Flow Characteristics in a Tight-Lattice Fuel Bundle, Proc. International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003) (CD-ROM), 1128 (2003)
H. Yoshida, M. Kureta, K. Kitou, K. Takase, H. Akimoto, Numerical simulation of the void drift using interface tracking method, Proc. of the 10th Int. Topical Meeting on Nucl. Reactor Thermal Hydraulics (NURETH10) (CD-ROM), E00208 (2003)
H. Yoshida, T. Nagayoshi, K. Takase and H. Akimoto, Verification of A Detailed Two-Phase Flow Analysis Code Based on an Advanced Interface-Tracking Method (I) - Detail of Numerical Method and Analysis of Liquid Film Falling down on Inclined Flat Plate -, Proc. of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Operation and Safety (NUTHOS-6) (CD-ROM), N6P266 (2004)
K. Kitou, M. Chaki, T. Nagayoshi, H. Yoshida and H. Akimoto, Verification of a detailed two-phase flow analysis code based on an advanced interface-tracking method (II) - Analysis of single-channel single bubble flow experiments -, Proc. of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Operation and Safety (NUTHOS-6) (CD-ROM), N6P245 (2004)
T. Nagayoshi, H. Yoshida, K. Takase and H. Akimoto, Verification of a detailed two-phase flow analysis code based on an advanced interface-tracking method (III) ? Analysis of Air Slug Deformation and Separation due to cross flow -, Proc. of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Operation and Safety (NUTHOS-6) (CD-ROM), N6P218 (2004)
H. Yoshida, K. Takase, Y. Ose, H. Tamai and H. Akimoto, Large-Scale Water-Vapor Two-Phase Flow Simulation in Advanced Light Water Reactor Cores, Proc. of 2004 International Congress on Advanced in Nuclear Power Plants (ICAPP'04) (CD-ROM), 4052 (2004)
H. Yoshida, H. Tamai, K. Takase, T. Nagayoshi and H. Akimoto, Development of Predictable Technology for Thermal/Hydraulic Performance of Reduced-Moderation Water Reactors (1) ? Master Plan -,, Proc. of 2004 International Congress on Advanced in Nuclear Power Plants (ICAPP'04) (CD-ROM), 4055 (2004)
H. Yoshida, H. Tamai, K. Takase, T. Nagayoshi and H. Akimoto, Development of Predictable Technology for Thermal/Hydraulic Performance of Reduced-Moderation Water Reactors (3) ? Current Status of Development of Three-Dimensional Two-Phase Flow Simulation Method -, Proc. of 2004 International Congress on Advanced in Nuclear Power Plants (ICAPP'04) (CD-ROM), 4057 (2004)
H. Yoshida, T Nagayoshi, H. Tamai, K. Takase and H. Akimoto, Numerical Simulation of Single Bubble Behavior in Rod Bundle with Interface Tracking Method, Proc. Fourth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS4) NTHAS4-063 (2004)
H. Yoshida, Y. Ose and K. Takase, Development of a Large-Scale Numerical Simulation Method on Water-Vapor Two-Phase Flow through Light-Water Reactor Cores, Proc. Fourth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS4) NTHAS4-064 (2004)
H. Yoshida, H. Tamai, A. Ohnuki, K. Takase and H. Akimoto, Current Status of Thermal/Hydraulic Feasibility Project for Reduced-Moderation Water Reactor(2)-Development of Two-Phase Flow Simulation Code with Advanced Interface-Tracking Method-, Proc. of International Congress on Advances in Nuclear Power Plants (ICAPP’05) 5156 (2005)
H. Yoshida, A. Ohnuki, T. Misawa, K. Takase and H. Akimoto, Development of Analytical Procedures on Two-Phase Flow in Tight-Lattice Fuel Bundles for Innovative Water Reactor for Flexible Fuel Cycle(FLWR), Proc. 2006 International Congress on Advanced in Nuclear Power Plants (ICAPP'06),6169, (2006)
H. Yoshida, T. Nagayoshi, K. Takase and H. Akimoto, Development of design technology on thermal-hydraulic performance in tight-lattice rod bundles: IV‐Numerical Evaluation of Fluid Mixing Phenomena in Boiling Water Reactor using Advanced Interface-Tracking Method‐, 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), ICONE15-10532 (2007)
T. Misawa, H. Yoshida and H. Akimoto, Development of design technology on thermal-hydraulic performance in tight-lattice rod bundles: V‐Large Paralleled Simulation by the Advanced Two-Fluid Model Code‐, Proc. of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), ICONE15-10543 (2007)
W. Zhang, H. Yoshida, Y. Ose et al. Numerical investigation of cross flow phenomena in a tight-lattice rod bundle using advanced interface tracking method, Proc. of 15th International Conference on Nuclear Engineering(ICONE-15), ICONE15-10082 (2007)
H. Yoshida, T. Misawa, K. Takase and H. Akimoto, Numerical Evaluation of Fluid Mixing Phenomena in Boiling Water Reactor Using Advanced Interface-Tracking Method, Proc. of FEDSM2007, （CD-ROM）, FEDSM2007-37302 (2007)
H. Yoshida, T. Nagayoshi, K. Takase and H. Akimoto, Analytical Procedure on Fluid Mixing Phenomena in Boiling Water Reactor Core with Advanced Interface Tracking Method, Proc. of FEDSM2007 (CD-ROM), FEDSM2007-37675 (2007)
T. Misawa, H. Yoshida, H. Tamai and K. Takase, Numerical Analysis of Heat Transfer Test of Supercritical Water in a Tube using the Three-Dimensional Two-Fluid Model Code, Proc. of 16th International Conference on Nuclear Engineering (ICONE-16) (CD-ROM), ICONE16-48690 (2008)
W. Zhang, H. Yoshida and K. Takase, Modeling of Pressure Fluctuation with Cross Flow in a Tight-Lattice Rod Bundle, Proc. of 16th International Conference on Nuclear Engineering (ICONE-16) (CD-ROM), ICONE16-48589 (2008)
H. Yoshida, T. Misawa and K. Takase, Numerical Simulation oｆ Boiling Two-Phase Flow in Tight-Lattice Rod Bundle by 3-Dimensional Two-Fluid Model Code ACE-3D, Proc. of 16th International Conference on Nuclear Engineering (ICONE-16) (CD-ROM), ICONE16-48715 (2008)
2. Acquisition of analysis code verification data
Large-scale test under high pressure
M. Kureta, H. Tamai, A. Ohnuki, T. Sato, W. Liu, H. Akimoto, “Critical Power Experiment with a Tight-Lattice 37-Rod Bundle”, JNST, 43, 2, 198-205, (2006).
H. Tamai, M. Kureta, W. Liu, T. Sato, A. Ohnuki, H. Akimoto, “Gap Width Effect on Critical Power based on Tight-Lattice 37-Rod Bundle Experiments”, JNST, 44, 1, 54-63, (2007).
H. Tamai, M. Kureta, W. Liu, T. Sato, T. Nakatsuka, A. Ohnuki and H. Akimoto, “Effect of Rod Bowing on Critical Power Based on Tight-Lattice 37-Rod Bundle Experiments”, JNST, 45, 6, 567-574, (2008).
H. Tamai, M. Kureta, H. Yoshida and H. Akimoto, “Pressure drop characteristics in tight-lattice rod bundles for reduced-moderation water reactors”, JSME International Journal, 47, 2, 293-298, (2004).
H. Tamai, M. Kureta, A. Ohnuki, T. Sato, H. Akimoto, “Pressure Drop Experiments using Tight-Lattice 37-Rod Bundles”, JNST, 43, 6, 1-8, (2006).
Conference:
M. Kureta, W. Liu, H. Tamai, A. Ohnuki, T. Mitutake and H. Akimoto, "Development of Predictable Technology for Thermal/Hydraulic Performance of Reduced-Moderation Water Reactors (2) - Large-scale Thermal/Hydraulic Test and Model Experiments-", Proc. ICAPP'04, No.4056, Pittsburgh, USA, June, 13-17 (2004).
H. Tamai, A. Ohnuki, M. Kureta, W. Liu, T. Sato, H. Akimoto, “Current Status of Thermal/Hydraulic Feasibility Project for Reduced-Moderation Water Reactor (1) - Large-Scale Thermal/Hydraulic Test ?“, Proc. ICAPP’05, No. 5157, Seoul Korea, May 15-19, (2005).
H. Tamai, W. Liu, M. Kureta, T. Sato, T. Nakatsuka, A. Ohnuki, H. Akimoto, “Critical Power Test of Rod-Bowing Effect in a Tight-Lattice Bundle”, 5th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS5), No. E005, Jeju Korea, (2006).
3. Development of measurement technology on thermal-hydraulics
H. Tamai, M. Kureta, W. Liu, T. Sato, A. Ohnuki and H. Akimoto, "Gap Width Effect on Critical Power based on Tight-Lattice 37-Rod Bundle Experiments, J. Nuclear Science and Technology, Vol. 44-1, pp.54-63, (2007).
W. Liu, M. Kureta, H. Yoshida, A. Ohnuki and H. Akimoto, "An Improved Critical Power Correlation for Tight-Lattice Rod Bundles", J. Nuclear Science and echnology, Vol. 44-4, pp.558-571, (2007).
W. Liu, M. Kureta, H. Tamai, A. Ohnuki and H. Akimoto, "Critical Power Characteristics in 37-Rod Tight-Lattice Bundles under Transient Conditions", J. Nuclear Science and Technology, Vol. 44-9, pp.1172-1181, (2007).
A. Ohnuki, M. Kureta, H. Yoshida, H. Tamai, W. Liu, T. Misawa, K. Takase and H. Akimoto, "Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles : I-Master Plan and Executive Summary", JSME J. Power and Energy Systems, Vol.2-1, pp.229-239, (2008).
WW. Liu, H. Tamai, M. Kureta, A. Ohnuki, K. Takase and H. Akimoto, "Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles : II - Rod Bowing Effect on Boiling Transition", JSME J. Power and Energy Systems, Vol.2-1, pp.240-249, (2008).
M. Kureta, "Development of a Neutron Radiography Three-Dimensional Computed Tomography System for Void Fraction Measurement of Boiling Flow in Tight Lattice Rod Bundles", M. Kureta, JSME J. Power and Energy Systems, Vol.1-3, pp.211-224, (2007).
M. Kureta, "Experimental Study of Three-Dimensional Void Fraction Distribution in Heated Tight-Lattice Rod Bundles Using Three-Dimensional Neutron Tomography", JSME J. Power and Energy Systems, Vol.1-3, pp.225-238, (2007).
M. Kureta, H. Tamai, H. Yoshida, A. Ohnuki and H. Akimoto, "Development of Design Technology on Thermal-hydraulic Performance in
Tight-lattice Rod Bundles : V - Estimation of Void Fraction", JSME J. Power and Energy Systems, Vol.2-1, pp.271-282, (2008).