Numerical Analysis of Thermal Stratification in a Circular Pipe

Author:

Jo Jong Chull1,Kim Yun Il1,Choi Seok Ki2

Affiliation:

1. Korea Institute of Nuclear Safety, Taejon 305-338, Korea

2. Korea Atomic Energy Research Institute, Taejon 305-353, Korea

Abstract

This paper presents an effective numerical method for predicting the stratified flow in a horizontal circular pipe. The method employs a body-fitted, nonorthogonal grid system to accommodate the pipe wall of circular geometry and the interface of the two fluids at different temperatures, of which the level is variable. The transient behaviors of fluid flow and temperature distribution in the piping are simulated using the finite volume approach. The convection term is approximated by a higher-order bounded scheme named HLPA, which is known as a high-resolution and bounded discretization scheme. The cell-centered, nonstaggered grid arrangement is adopted and the resulting checkerboard pressure oscillation is prevented by the application of modified momentum interpolation scheme. The SIMPLE algorithm is employed for the pressure and velocity coupling. The new way of treating the unsteady conjugate heat transfer problem is presented. The present method has been applied to the stratified flow in the pressurizer surge line of the nuclear reactor, and the results have been discussed. In addition, this study has investigated the effects of level of the interface between the two stratified fluids on the transient evolution of temperature distributions in the piping wall.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference12 articles.

1. NRC Bulletin No. 88-08, 1988, “Thermal Stress in Piping Connected to Reactor Coolant System,” USNRC.

2. NRC Bulletin No. 88-11, 1988, “Pressurizer Surge Line Thermal Stratification,” USNRC.

3. Smith, W. R., Cassell, D. S., and Schlereth, E. P., 1988, “A Solution for the Temperature Distribution in a Pipe Wall Subjected to Internally Stratified Flow,” Proc., Joint ASME-ANS Nuclear Power Conf., Myrtle Beach, SC, pp. 45–50.

4. Talja, A., and Hansjosten, E., 1990, “Results of Thermal Stratification Tests in a Horizontal Pipe Line at the HDR-Facility,” Nucl. Eng. Des., 118, pp. 29–41.

5. Ensel, C., Colas, A., and Barthez, M., 1995, “Stress Analysis of a 900 MW Pressurizer Surge Line Including Stratification Effects,” Nucl. Eng. Des., 153, pp. 197–203.

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