Prediction Method of Countercurrent Flow Limitation in a Pressurizer Surge Line and Its Evaluation for a 1/10-Scale Model

Author:

Murase Michio1,Utanohara Yoichi2,Kusunoki Takayoshi2,Lucas Dirk3,Tomiyama Akio4

Affiliation:

1. Mem. ASME Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan e-mail:

2. Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan e-mail:

3. Helmholtz-Zentrum Dresden-Rossendorf, P.O. Box 510 119, Dresden 01314, Germany e-mail:

4. Kobe University, 1-1 Rokkodai, Nada-ku, Kobe-shi, Hyogo 657-8501, Japan e-mail:

Abstract

The method for predicting countercurrent flow limitation (CCFL) and its uncertainty in an actual pressurizer surge line of a pressurized water reactor (PWR) using 1/10-scale air–water experimental data, one-dimensional (1D) computations, and three-dimensional (3D) numerical simulations was proposed. As one step of the prediction method, 3D numerical simulations were carried out for countercurrent air–water flows in a 1/10-scale model of the pressurizer surge line to evaluate capability of the 3D simulation method and decide uncertainty of CCFL characteristics evaluated for the 1/10-scale model. The model consisted of a vertical pipe, a vertical elbow, and a slightly inclined pipe with elbows. In the actual 1/10-scale experiment, air supplied into the lower tank flowed upward to the upper tank and water supplied into the upper tank gravitationally flowed downward to the lower tank through the pressurizer surge line. In the 3D simulation, however, water was supplied from the wall surface of the vertical pipe to avoid effects of flooding at the upper end (the 3D simulation largely underestimated falling water flow rates at the upper end). Then, the flow pattern in the slightly inclined pipe was successfully reproduced, and the simulated CCFL values for the inclination angle of θ=0.6  deg (slope of 1/100) agreed well with the experimental CCFL data. The uncertainty among air–water experiments, 1D computations, and 3D simulations for the 1/10-scale model was dC=±0.015 for the CCFL constant of C=0.50. The effects of θ (θ=0,1.0 deg) on CCFL characteristics were simulated and discussed.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference24 articles.

1. Richter, H. J., Wallis, G. B., Carter, K. H., and Murphy, S. L., 1978, “Deentrainment and Countercurrent Air-Water Flow in a Model PWR Hot-Leg,” U. S. Nuclear Regulatory Commission, NRC-0193-9.

2. Two-Phase Flow Phenomena in Full-Scale Reactor Geometry;Nucl. Eng. Des.,1993

3. Geffraye, G., Bazin, P., Pichon, P., and Bengaouer, A., 1995, “CCFL in Hot Legs and Steam Generators and Its Prediction With the CATHARE Code,” Proceedings of the 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-7), Saratoga Springs, NY, Sep. 10–15, American Nuclear Society, La Grange Park, IL, pp. 815–826.

4. Experimental Investigation of Countercurrent Flow Limitation (CCFL) in a Large-Diameter Hot-Leg Geometry: A Derailed Description of CCFL Mechanisms, Flow Patterns and High-Quality HSC Imaging of the Interfacial Structure in a 1/3.9 Scale of PWR Geometry;Nucl. Eng. Des.,2014

5. Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling (I) Air-Water Tests for 1/15-Scale Model of a PWR Hot Leg;J. Nucl. Sci. Technol.,2010

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