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Title: CFD Modeling of Sodium-Oxide Deposition in Sodium-Cooled Fast Reactor Compact Heat Exchangers

Conference ·
OSTI ID:1259204

The possible use of compact heat exchangers (HXs) in sodium-cooled fast reactors (SFR) employing a Brayton cycle is promising due to their high power density and resulting small volume in comparison with conventional shell-and-tube HXs. However, the small diameter of their channels makes them more susceptible to plugging due to Na2O deposition during accident conditions. Although cold traps are designed to reduce oxygen impurity levels in the sodium coolant, their failure, in conjunction with accidental air ingress into the sodium boundary, could result in coolant oxygen levels that are above the saturation limit in the cooler parts of the HX channels. This can result in Na2O crystallization and the formation of solid deposits on cooled channel surfaces, limiting or even blocking coolant flow. The development of analysis tools capable of modeling the formation of these deposits in the presence of sodium flow will allow designers of SFRs to properly size the HX channels so that, in the scenario mentioned above, the reactor operator has sufficient time to detect and react to the affected HX. Until now, analytical methodologies to predict the formation of these deposits have been developed, but never implemented in a high-fidelity computational tool suited to modern reactor design techniques. This paper summarizes the challenges and the current status in the development of a Computational Fluid Dynamics (CFD) methodology to predict deposit formation, with particular emphasis on sensitivity studies on some parameters affecting deposition.

Research Organization:
Westinghouse Electric Company
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Contributing Organization:
Westinghouse Electric Company, Argonne National Laboratory
DOE Contract Number:
NE0000611
OSTI ID:
1259204
Report Number(s):
DOE-WEC-0000611-3
Resource Relation:
Conference: 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH), Chicago IL, Aug. 30-Sept 4, 2015
Country of Publication:
United States
Language:
English