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[en] The Westinghouse Electric Corporation D4 steam generator design was analyzed from a thermal-hydraulic point of view using the 3D PHOENICS computer code. Void fraction, velocity and enthalpy distributions were obtained in the U-tube riser. The boundary conditions of primary side were provided by SMUP 1D code. The calculations were carried out for present operating conditions of nuclear power plant Krsko. (author)
Source
Stritar, A.; Jencic, I. (Nuclear Society of Slovenia (Slovenia)) (eds.); European Nuclear Society (Switzerland); Ministry of Science and Technology of Slovenia, Ljubljana (Slovenia); Jozef Stefan Institute, Ljubljana (Slovenia); Nuclear Safety Administration of Slovenia, Ljubljana (Slovenia); 615 p; ISBN 961-90004-9-8; 
; 1995; p. 464-471; 2. Regional Meeting on Nuclear Energy in Central Europe; Portoroz (Slovenia); 11-14 Sep 1995; 8 refs., 4 figs., 1 tab.
; 1995; p. 464-471; 2. Regional Meeting on Nuclear Energy in Central Europe; Portoroz (Slovenia); 11-14 Sep 1995; 8 refs., 4 figs., 1 tab.