Temperature field progression in annular tube around heated rod in respect to the mass flow of coolant
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Lávička, David
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Vysoká škola báňská - Technická univerzita Ostrava
Abstract
The paper looks into liquid flow simulation in the annular tube around the heated rod. The numerical simulation serves primarily the purpose of describing the temperature field in the annular tube that represents a simplified model of a nuclear reactor fuel rod. The fuel rod model uses several configurations of spacers which affect the flow of coolant - water - in the annular flow channel. For selected variants of spacers, temperature fields have been mutually compared in respect to various mass flow characteristics of the coolant.
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Sborník vědeckých prací Vysoké školy báňské - Technické univerzity Ostrava. Řada strojní. 2010, roč. 56, č. 3, s. 103-108 : il.