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Temperature and flow distributions in sodium-heated large straight tube steam generator by numerical methods

Kisohara, Naoyuki ; Moribe, Takeshi; Sakai, Takaaki

A sodium heated steam generator (SG) for the Japanese future commercialized fast reactor is a straight double-wall-tube type. The SG is large-sized by economics of scale. Large-sized heat exchanger components are prone to have non-uniform flow and temperature distributions. These mal-distributions cause tubes thermal expansion mismatch and it might lead to tube buckling or tube to tube-sheet junction failure in straight tube type SGs. The temperature profiles in the SG are examined by numerical methods, and the flow distribution devices are designed to prevent these issues. Multi-dimensional thermal-hydraulic codes "FLUENT" and "MSG" are used to predict tube temperature distributions, and the thermal loads on tubes are obtained by the structural code "FINAS". These codes have revealed that the sodium flow is distributed uniformly by the flow distributors, and that the tube thermal loads remain within the allowable range for the tubes and the junctions structural integrity.

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Category:Nuclear Science & Technology

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