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

Abstract

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.

Authors:
; ;
Publication Date:
Research Org.:
Battelle Pacific Northwest Labs., Richland, WA (USA)
OSTI Identifier:
5766168
Report Number(s):
EPRI-NP-1162
TRN: 79-022142
DOE Contract Number:  
EY-76-C-06-1830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; STEAM GENERATORS; HEAT TRANSFER; HYDRAULICS; COMPUTER CALCULATIONS; HYDRODYNAMICS; TWO-PHASE FLOW; BOILERS; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; MECHANICS; REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210200* - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Stewart, C W, Thurgood, M J, and Mayer, D W. Analysis of single- and two-phase flow fields around PWR steam generator tube support plates. United States: N. p., 1979. Web.
Stewart, C W, Thurgood, M J, & Mayer, D W. Analysis of single- and two-phase flow fields around PWR steam generator tube support plates. United States.
Stewart, C W, Thurgood, M J, and Mayer, D W. 1979. "Analysis of single- and two-phase flow fields around PWR steam generator tube support plates". United States.
@article{osti_5766168,
title = {Analysis of single- and two-phase flow fields around PWR steam generator tube support plates},
author = {Stewart, C W and Thurgood, M J and Mayer, D W},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/5766168}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {8}
}

Technical Report:
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