. "6"^^ . . "189770" . . "[2A7392707468]" . "RIV/49777513:23210/11:43896696" . "RIV/49777513:23210/11:43896696!RIV12-GA0-23210___" . "World Academy of Science Engineering and Technology" . . . . . . "23210" . . "7" . "2010-376X" . "1"^^ . "CFD simulation the thermal-hydraulic characteristic within fuel rod bundle near grid spacers" . . "CFD, fuel rod model, heat transfer, spacer"@en . "1"^^ . "CFD simulation the thermal-hydraulic characteristic within fuel rod bundle near grid spacers"@en . . "This paper looks into detailed investigation of thermal-hydraulic characteristics of the flow field in a fuel rod model, especially near the spacer. The area investigate represents a source of information on the velocity flow field, vortex, and on the amount of heat transfer into the coolant all of which are critical for the design and improvement of the fuel rod in nuclear power plants. The flow field investigation uses three-dimensional Computational Fluid Dynamics (CFD) with the Reynolds stresses turbulence model (RSM). The fuel rod model incorporates a vertical annular channel where three different shapes of spacers are used; each spacer shape is addressed individually. These spacers are mutually compared in consideration of heat transfer capabilities between the coolant and the fuel rod model. The results are complemented with the calculated heat transfer coefficient in the location of the spacer and along the stainless-steel pipe." . . . "CFD simulation the thermal-hydraulic characteristic within fuel rod bundle near grid spacers"@en . "FR - Francouzsk\u00E1 republika" . . "P(GP101/09/P056), S" . "L\u00E1vi\u010Dka, David" . . "79" . "This paper looks into detailed investigation of thermal-hydraulic characteristics of the flow field in a fuel rod model, especially near the spacer. The area investigate represents a source of information on the velocity flow field, vortex, and on the amount of heat transfer into the coolant all of which are critical for the design and improvement of the fuel rod in nuclear power plants. The flow field investigation uses three-dimensional Computational Fluid Dynamics (CFD) with the Reynolds stresses turbulence model (RSM). The fuel rod model incorporates a vertical annular channel where three different shapes of spacers are used; each spacer shape is addressed individually. These spacers are mutually compared in consideration of heat transfer capabilities between the coolant and the fuel rod model. The results are complemented with the calculated heat transfer coefficient in the location of the spacer and along the stainless-steel pipe."@en . . . "CFD simulation the thermal-hydraulic characteristic within fuel rod bundle near grid spacers" . .