Experimental study on thermo-hydraulics instability on natural circulation BWR concept
AbstractAbstract
[en] Experimental results of studying the thermohydraulic instability of the modes of water natural convection under conditions of the BWR reactor startup are presented. Effect of water under heating at the channel input and the effect of pressure in the system are studied. The diagrams of the safe modes of the coolant flow during the BWR reactor startup are constructed by means of the obtained data
Original Title
Issledovanie teplogidravlicheskoj nestabil'nosti estestvennoj konvektsii teplonositelya v reaktore BWR; underheating
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Source
Translated form English: Bull. Res. Lab. Nucl. Reactor, 2003, v. 27, p. 9; 4 refs., 3 figs.
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Journal Article
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Translation
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Descriptors (DEI)
Descriptors (DEC)
CONVECTION, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, FLUID FLOW, FLUID MECHANICS, HEAT TRANSFER, HYDROGEN COMPOUNDS, MASS TRANSFER, MECHANICS, OXYGEN COMPOUNDS, POWER REACTORS, PRESSURE RANGE, PRESSURE RANGE MEGA PA, REACTORS, SAFETY, START-UP, TEMPERATURE RANGE, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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