Published November 1986 | Version v1
Journal article

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

  • 1. Korea Advanced Institute of Science and Technology, Dept. of Nuclear Engineering, P.O. Box 150, Chongryang, Seoul

Description

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,θ,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

Additional details

Publishing Information

Journal Title
Nucl. Technol.
Journal Volume
75
Journal Issue
2
Series
Nucl. Technol.
Journal Page Range
205-214
ISSN
0029-5450
CODEN
NUTYB