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Title: Three-dimensional two-fluid code for U-tube steam generator thermal design analysis

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5043997

A computer code, FAUST (Flow Analysis of U-tube Steam generators), for U-tube steam generator design analysis is developed on the basis of the pressurized water reactor core transient analysis code, THERMIT. The original (x,y,z) coordinates used in THERMIT are transformed into the cylindrical (r,theta,z) coordinates for FAUST, which are better fitted in the geometry of steam generators. To couple the primary side with the secondary side, a one-dimensional tube representative of a computational cell in the heat transfer model is developed with a geometrical mapping between the primary and secondary sides. The special unitary group SU(2) is used to treat the complex geometry of the U-bend region for frictional wall force. A form loss model for tube support plates in two-phase flow is implemented in the code. The steam dome model developed here enables us to consider the different amounts of feedwater distributed into the hot and cold sides of the downcomer.

Research Organization:
Korea Advanced Institute of Science and Technology, Dept. of Nuclear Engineering, P.O. Box 150, Chongryang, Seoul
OSTI ID:
5043997
Journal Information:
Nucl. Technol.; (United States), Vol. 75:2
Country of Publication:
United States
Language:
English