Advances in the modeling of cladding heat transfer and critical heat flux in boiling water reactor fuel assemblies

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12

Volumn , Issue , 2007, Pages

  Ioilev, Andrey ^a   Samigulin, Maskhud ^a   Ustinenko, Vasily ^a   Kucherova, Polina ^b   Tentner, Adrian ^c   Lo, Simon ^d   Splawski, Andrew ^d  

^a RUSSIAN FEDERAL NUCLEAR CENTER VNIIEF   (Russian Federation)

^b Sarov Laboratories   (Russian Federation)

^c ARGONNE NATIONAL LABORATORY   (United States)

^d SIEMENS AG   (Germany)

Author keywords

Boiling water reactor; Computational fluid dynamics; Critical heat flux; Two phase flow

Indexed keywords

BOILING WATER REACTORS; COMPUTATIONAL FLUID DYNAMICS; COOLANTS; HEAT FLUX; NUCLEAR FUEL CLADDING; TWO PHASE FLOW;

CLADDING TO COOLANT HEAT TRANSFER; FLOW MODELING;

HEAT TRANSFER;

EID: 44349109601     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (12)

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