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AbstractAbstract
[en] In this paper experimental coolant loop is presented. Model is capable to simulate the operation of primary coolant loop of nuclear power plant. Thermohydraulic transients are initiated by power excursions or coolant flow changes. (author)
Original Title
Eksperimentalni model rashladnog kruga reaktora
Primary Subject
Source
1987; 8 p; Society for Electronics,Telecommunications, Automation, and Nuclear Engineering; Belgrade (Yugoslavia); 31. Conference - ETAN'87: Society for Electronics, Telecommunications, Automation, and Nuclear Engineering; ETAN'87: 31. Konferencija za elektroniku, telekomunikacije, automatiku i nuklearnu tehniku; Bled (Yugoslavia); 1-5 Jun 1987; Also available from the Institute of Nuclear Sciences VINCA; 3 refs., 3 figs.
Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue