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AbstractAbstract
[en] A computer code ALMOD 3W3 to analyze the transients in which reverse flow in the primary loop of nuclear power plant may occur has been developed. The method to calculate the fluid dynamics in NRC system is presented. The locked rotor accident in one coolant loop is analyzed. (author)
Original Title
Primjena programa ALMOD u analizi prijelaznih pojava sa reverzibilnim protokom u primarnom krugu nuklerne elektrane
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1989; 8 p; Society for Electronics,Telecommunications, Computers, Automation, and Nuclear Engineering; Belgrade (Yugoslavia); 33. Conference - ETAN '89: Society for Electronics, Telecommunications, Computers, Automation, and Nuclear Engineering; ETAN '89: 33. Konferencija za elektroniku, telekomunikacije, racunarstvo, automatiku i nuklearnu tehniku; Novi Sad (Yugoslavia); 12-17 Jun 1989; Also available from the Institute of Nuclear Sciences VINCA; 4 refs., 4 figs.
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