Experimental Investigations and Numerical Studies of Two-Phase Countercurrent Flow Limitation in a Pressurized Water Reactor: A Review

Gas-liquid two-phase countercurrent flow limitation (CCFL) phenomena widely exist in nuclear power plants. In particular, the gas-liquid countercurrent flow limitation phenomena in a pressurized water reactor (PWR) during a loss-of-coolant accident (LOCA) or a small-break loss-of-coolant accident (SBLOCA) play an important role in nuclear reactor safety research. Over several decades, a series of experimental investigations and numerical studies have been carried out to study the CCFL phenomena in a PWR. For the experimental investigations, numerous experiments have been conducted, and different CCFL mechanisms and CCFL characteristics have been obtained in various test facilities simulating different scenarios in a PWR. The CCFL phenomena are affected by many factors, such as geometrical characteristics, liquid flow rates, and fluid properties. For the numerical studies, more and more numerical models were presented and applied to the calculations of two-phase countercurrent flow over the past several decades. It is considered that the computational fluid dynamics (CFD) tools can simulate most of the two-phase flow configurations encountered in nuclear power plants. In this paper, the experimental investigations and the numerical studies on two-phase countercurrent flow limitation in a PWR are comprehensively reviewed. This review provides a further understanding of CCFL in a PWR and gives directions regarding future studies. It is found that relatively fewer investigations using steam-water under high system pressures are performed due to the limitation of the test facilities and test conditions. There are a number of numerical studies on countercurrent two-phase flow in a PWR hot leg geometry, but the simulations in other flow channels were relatively rare. In addition, almost all of the numerical simulations do not include heat and mass transfer. Thus, it is necessary to investigate the effects of heat and mass transfer experimentally and numerically. Furthermore, it is of significance to perform numerical simulations for countercurrent two-phase flow with a fine computational grid and suitable models to predict the formation of small waves and the details in two-phase flow.

Automated summary

Gas-liquid two-phase countercurrent flow limitation (CCFL) phenomena are commonly observed in nuclear power plants, especially in pressurized water reactors (PWR) during loss-of-coolant accidents. Experimental investigations and numerical studies have been conducted to understand CCFL phenomena in PWRs, with different CCFL mechanisms and characteristics obtained. Factors such as geometrical characteristics, liquid flow rates, and fluid properties influence CCFL phenomena. Computational fluid dynamics (CFD) tools have been used to simulate two-phase flow configurations in nuclear power plants. This review comprehensively examines experimental investigations and numerical studies of two-phase countercurrent flow limitation in PWRs, providing further understanding and directions for future studies. It highlights the need to investigate heat and mass transfer effects and improve numerical simulations for finer prediction of wave formation and two-phase flow details.