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Flow distribution among parallel heated channels

โœ Scribed by Alan R. Gruber; Seymour C. Hyman


Publisher
American Institute of Chemical Engineers
Year
1956
Tongue
English
Weight
607 KB
Volume
2
Category
Article
ISSN
0001-1541

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โœฆ Synopsis


Abstract

The coolant flow distribution among parallel tubes in a nuclear reactor (or boiler or heat exchanger) can be very sensitive to variations in heat input, dimensions, etc. Analytical expressions are given for partial derivatives which measure flow variations for several situations. The utility of orifices and valves in reducing flow sensitivity is discussed. Numerical results are reported for a system using water at supercritical pressurs with an eightfold expansion from inlet to outlet.


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