Evaluation of a numeric procedure for flow simulation of a 5 × 5 PWR rod bundle with a mixing vane spacer

Progress in Nuclear Energy

Volumn 53, Issue 8, 2011, Pages 1190-1196

  Navarro, Moysés A ^a   Santos, André A C ^b  

^a CENTRO DE DESENVOLVIMENTO DA TECNOLOGIA NUCLEAR   (Brazil)

^b FEDERAL UNIVERSITY OF MINAS GERAIS   (Brazil)

Author keywords

CFD; Nuclear fuel; Rod bundle; Spacer grid

Indexed keywords

ANTAGONIST EFFECTS; AXIAL VELOCITY; COMMERCIAL CODES; COMPUTATIONAL CAPACITY; COMPUTATIONAL DOMAINS; COMPUTATIONAL WORK; COOLANT FLOW; DYNAMIC FEATURES; EXPERIMENTAL STUDIES; FLOW CONDITION; FUEL ASSEMBLY; GEOMETRICAL CONFIGURATIONS; HEAT TRANSFER PERFORMANCE; INLET CONDITIONS; LOCAL HEAT TRANSFER; MESH REFINEMENT; MIXING VANE; NUMERICAL PROCEDURES; OPERATING POWER; REYNOLDS-AVERAGED NAVIER-STOKES; ROD BUNDLES; SPACER GRID; SUB-DOMAINS; SUBCHANNELS; SUBDOMAIN; SWIRL FLOW; THEORETICAL INVESTIGATIONS;

FLOW SIMULATION; HEAT TRANSFER; HIGH PRESSURE EFFECTS; NAVIER STOKES EQUATIONS; NUCLEAR FUELS; NUCLEATE BOILING; PRESSURIZED WATER REACTORS; REYNOLDS EQUATION; TURBULENCE MODELS; TWO PHASE FLOW;

COMPUTATIONAL FLUID DYNAMICS;

EID: 81455154480     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2011.08.002     Document Type: Conference Paper

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