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AbstractAbstract
[en] A model of thermohydraulics behaviour of reactor coolant is presented. Formulation of the model is based on drift-flux model concept of two-phase flow with four field equations. The results of the proposed model are compared with available data for the case of exponential decay flow in the channel. (author)
Original Title
Modeliranje ponasanja reaktorskog kanala u poremecenim uslovima rada
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1985; 7 p; Society for Electronics,Telecommunications, Automation, and Nuclear Engineering; Belgrade (Yugoslavia); 29. Conference - ETAN '85: Society for Electronics, Telecommunications, Computers, Automation and Nuclear Engineering; 29. Konferencija za ETAN; Nis (Yugoslavia); 3-7 Jun 1985; Also available from the Institute of Nuclear Sciences VINCA; 10 refs.
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Miscellaneous
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Conference
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