Analysis of single- and two-phase flow fields around PWR steam generator tube support plates

Technical Report · Wed Aug 01 00:00:00 EDT 1979

OSTI ID:5766168

Stewart, C W; Thurgood, M J; Mayer, D W

The thermal-hydraulic analysis of the Westinghouse Series 51 U-tube PWR steam generator using a newly developed two-fluid (UVUT) two-phase flow model is presented. The development of the model and current state of its constitutive modeling is described in detail and some initial data comparisons are presented. The two-fluid model was incorporated into the Battelle COBRA-IV code and the resulting developmental version is referred to as COBRA-TF (EPRI). The analysis of the Westinghouse steam generator concentrated on the local flow field a few inches above and below the tube support plates at various levels. A full-scale simulation of the entire steam generator was also performed to provide boundary conditions for the local analyses. Plots of the predicted vapor friction and velocity fields are presented for both simulations.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (USA)
• DOE Contract Number: EY-76-C-06-1830
• OSTI ID: 5766168
• Report Number(s): EPRI-NP-1162; TRN: 79-022142
• Country of Publication: United States
• Language: English

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