Single-phase convective heat transfer in rod bundles

Nuclear Engineering and Design

Volumn 238, Issue 4, 2008, Pages 848-858

  Holloway, Mary V ^a   Beasley, Donald E ^b   Conner, Michael E ^c  

^a UNITED STATES NAVAL ACADEMY   (United States)

^b Clemson University   (United States)

^c Westinghouse Nuclear Fuel   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

AXIAL FLOW; HYDRAULIC EQUIPMENT; NUCLEAR FUELS; PRESSURIZED WATER REACTORS; TURBULENT FLOW; WORKING FLUID PRESSURE INDICATORS;

CONVECTIVE HEAT TRANSFER; HEAT TRANSFER ENHANCEMENT; HYDRAULIC DIAMETERS; NUCLEAR FUEL RODS;

HEAT TRANSFER COEFFICIENTS;

EID: 40249098700     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2007.08.003     Document Type: Article

References (17)

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