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AbstractAbstract
[en] An analytical model was developed for the best estimate steady state thermal-hydraulic analysis of PWR core in WWER-1000 type reactor using COBRA-III-C computer code. The model rests broadly on the know-how, methods and philosophy of modelling the NPP Krsko core. (author)
Original Title
Termohidravlicna analiza sredice reaktorja VVER 1000 s programom COBRA-III-C
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1986; 8 p; Society for Electronics,Telecommunications, Automation, and Nuclear Engineering; Belgrade (Yugoslavia); 30. Conference - ETAN'86: Society for Electronics, Telecommunications, Automation, and Nuclear Engineering; 30. Konferencija za ETAN; Herceg Novi (Yugoslavia); 2-6 Jun 1986; Also available from the Institute of Nuclear Sciences VINCA; 7 refs., 4 figs., 2 tabs.
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Miscellaneous
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