Investigation on heat transfer non-uniformity in rod bundle
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[1] Y. Q. Yu,et al. Local thermal–hydraulic behaviour in tight 7-rod bundles , 2009 .
[2] E. Merzari,et al. Analysis of low Reynolds number turbulent flow phenomena in nuclear fuel pin subassemblies of tight lattice configuration , 2009 .
[3] Xu Cheng,et al. CFD ANALYSIS OF THERMAL-HYDRAULIC BEHAVIOR IN SCWR TYPICAL FLOW CHANNELS , 2008 .
[4] Xiaojing Liu,et al. A MIXED CORE FOR SUPERCRITICAL WATER-COOLED REACTORS , 2008 .
[5] Takamichi Iwamura,et al. Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics , 2007 .
[6] Yoshiaki Oka,et al. Numerical investigation of heat transfer in upward flows of supercritical water in circular tubes and tight fuel rod bundles , 2007 .
[7] Xu Cheng,et al. CFD analysis of thermal–hydraulic behavior of heavy liquid metals in sub-channels , 2006 .
[8] T. Okubo,et al. Optimization of seed-blanket type fuel assembly for reduced-moderation water reactor , 2003 .
[9] D. Struwe,et al. High performance light water reactor , 2003 .
[10] T. Downar,et al. Thorium Fuel Performance in a Tight-Pitch Light Water Reactor Lattice , 2002 .
[11] L. Meyer,et al. Experimental investigation of turbulent transport of momentum and energy in a heated rod bundle , 1998 .
[12] Yoshiaki Oka,et al. A Direct-Cycle, Supercritical- Water-Cooled Fast Breeder Reactor , 1994 .
[13] Werner Oldekop,et al. General Features of Advanced Pressurized Water Reactors with Improved Fuel Utilization , 1982 .
[14] A. V. Zhukov,et al. Azimuthal temperature nonuniformity in a regular array of fuel elements for turbulent liquid metal flow , 1977 .
[15] P. A. Ushakov. Calculation of the temperature fields of bundles of fuel elements in axial turbulent flows of heat-transfer media with vanishingly small Prandtl numbers , 1975 .
[16] H. C. Berry,et al. Heat transfer to liquid metals flowing turbulently and longitudinally through closely spaced rod bundles: Part II. Uniform heat flux at the inner surface of the cladding☆ , 1972 .
[17] R. Nijsing,et al. ANALYSIS OF LIQUID METAL HEAT TRANSFER IN ASSEMBLIES OF CLOSELY SPACED FUEL RODS. , 1969 .
[18] P. A. Ushakov,et al. Heat exchange during the flow of mercury and water in a tightly packed rod pile , 1961 .
[19] Xiaojing Liu,et al. Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly , 2009 .
[20] S. Koshizuka,et al. Supercritical-pressure, light-water-cooled reactors for economical nuclear power plants , 1998 .
[21] T. Krauss,et al. Characteristics of turbulent velocity and temperature in a wall channel of a heated rod bundle , 1996 .
[22] P. A. Ushakov,et al. Investigation of temperature fields in the flow of a sodium-potassium melt in the cell of a compact rod bundle , 1975 .