Numerically simulating the thermal-hydraulic characteristics within the fuel rod bundle using CFD methodology

Nuclear Engineering and Design

Volumn 240, Issue 10, 2010, Pages 3078-3086

  Liu, C C ^a   Ferng, Y M ^a  

^a NATIONAL TSING HUA UNIVERSITY   (Taiwan)

Author keywords

[No Author keywords available]

Indexed keywords

CFD MODELS; CFD SIMULATIONS; COMPUTER PROCESSING POWER; FLOW-MIXING; FUEL RODS; GRID DESIGN; HEAT TRANSFER CAPABILITY; HEAT TRANSFER CHARACTERISTICS; HEAT TRANSFER ENHANCEMENT; NU NUMBER; NUMBER DISTRIBUTION; REYNOLDS; REYNOLDS STRESS; ROD BUNDLES; SIMULATION RESULT; SPACER GRID; THERMAL HYDRAULICS; THREE-DIMENSIONAL (3D); TURBULENT MIXING;

BUOYANCY; DESIGN; HEAT TRANSFER; HYDRAULICS; LEAKAGE (FLUID); NUCLEAR POWER PLANTS; REYNOLDS NUMBER; STANDARDS; THREE DIMENSIONAL; TURBULENCE MODELS;

COMPUTATIONAL FLUID DYNAMICS;

EID: 77957690855     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2010.05.021     Document Type: Conference Paper

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