A circumferentially non‐uniform fuel model and its application to thermal‐hydraulic code
暂无分享,去创建一个
Xu Cheng | Xiaojing Liu | Ting Yang | Xu Cheng | Xiaojing Liu | Ting Yang
[1] Q. Bi,et al. Experimental investigation of heat transfer from a 2 × 2 rod bundle to supercritical pressure water , 2014 .
[2] T. Okubo,et al. Optimization of seed-blanket type fuel assembly for reduced-moderation water reactor , 2003 .
[3] R. Nijsing,et al. ANALYSIS OF LIQUID METAL HEAT TRANSFER IN ASSEMBLIES OF CLOSELY SPACED FUEL RODS. , 1969 .
[4] Xu Cheng,et al. CFD analysis of thermal–hydraulic behavior of heavy liquid metals in sub-channels , 2006 .
[5] S. Koshizuka,et al. Supercritical-pressure, Once-through Cycle Light Water Cooled Reactor Concept , 2001 .
[6] Robert Hill,et al. Preliminary core design studies for the advanced burner reactor over a wide range of conversion ratios. , 2008 .
[7] Xu Cheng,et al. Investigation on heat transfer non-uniformity in rod bundle , 2013 .
[8] Meng Zhao,et al. Experimental study on heat transfer of supercritical water flowing downward in circular tubes , 2014 .
[9] T. Krauss,et al. Characteristics of turbulent velocity and temperature in a wall channel of a heated rod bundle , 1996 .
[10] L. Meyer,et al. Experimental investigation of turbulent transport of momentum and energy in a heated rod bundle , 1998 .
[11] T. Schulenberg,et al. Heat transfer at supercritical pressures. Literature review and application to an HPLWR , 2001 .
[12] Douglas C. Crawford,et al. Fuels for sodium-cooled fast reactors: US perspective , 2007 .
[13] Xiaojing Liu,et al. Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly , 2009 .
[14] S. Koshizuka,et al. Supercritical-pressure, light-water-cooled reactors for economical nuclear power plants , 1998 .
[15] E. Merzari,et al. Analysis of low Reynolds number turbulent flow phenomena in nuclear fuel pin subassemblies of tight lattice configuration , 2009 .
[16] P. A. Ushakov,et al. Heat exchange during the flow of mercury and water in a tightly packed rod pile , 1961 .
[17] 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 .
[18] Werner Oldekop,et al. General Features of Advanced Pressurized Water Reactors with Improved Fuel Utilization , 1982 .
[19] D. Struwe,et al. High performance light water reactor , 2003 .
[20] Takamichi Iwamura,et al. Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics , 2007 .
[21] Y. Q. Yu,et al. Local thermal–hydraulic behaviour in tight 7-rod bundles , 2009 .
[22] Xiaojing Liu,et al. A MIXED CORE FOR SUPERCRITICAL WATER-COOLED REACTORS , 2008 .