scholarly journals CFD ANALYSIS OF TURBULENT JET BEHAVIOR INDUCED BY A STEAM JET DISCHARGED THROUGH A VERTICAL UPWARD SINGLE HOLE IN A SUBCOOLED WATER POOL

2010 ◽  
Vol 42 (4) ◽  
pp. 382-393 ◽  
Author(s):  
Hyung-Seok Kang ◽  
Chul-Hwa Song
Author(s):  
Takayuki Suzuki ◽  
Hiroyuki Yoshida ◽  
Naoki Horiguchi ◽  
Sota Yamamura ◽  
Yutaka Abe

Abstract In the severe accident (SA) of nuclear reactors, fuel and components melt, and melted materials fall to a lower part of a reactor vessel. In the lower part of a reactor vessel, in some sections of the SAs, it is considered that there is a water pool. Then, the melted core materials fall into a water pool in the lower plenum as a jet. The molten material jet is broken up, and heat transfer between molten material and coolant may occur. This process is called a fuel-coolant interaction (FCI). FCI is one of the important phenomena to consider the coolability and distribution of core materials. In this study, the numerical simulation of jet breakup phenomena with a shallow pool was performed by using the developed method (TPFIT). We try to understand the hydrodynamic interaction under various, such as penetration, reach to the bottom, spread, accumulation of the molten material jet. Also, we evaluated a detailed jet spread behavior and examined the influence of lattice resolution and the contact angle. Furthermore, the diameters of atomized droplets were evaluated by using numerical simulation data.


2017 ◽  
Vol 2 ◽  
pp. 80-86 ◽  
Author(s):  
Satyajit Kumar Shukla ◽  
A.M. Naveen Samad ◽  
Sumana Ghosh

2009 ◽  
Vol 239 (12) ◽  
pp. 2849-2863 ◽  
Author(s):  
Young-Tae Moon ◽  
Hee-Do Lee ◽  
Goon-Cherl Park

2010 ◽  
Vol 240 (10) ◽  
pp. 3259-3266 ◽  
Author(s):  
Xin-Zhuang Wu ◽  
Jun-Jie Yan ◽  
Wen-Jun Li ◽  
Dong-Dong Pan ◽  
Guang-Yao Liu

2012 ◽  
Vol 134 (3) ◽  
Author(s):  
Chul-Hwa Song ◽  
Seok Cho ◽  
Hyung-Seok Kang

The phenomena of direct contact condensation (DCC) of a steam jet submerged in a water pool occur because of the actuation of steam discharging devices in many industrial processes. There are practically two kinds of technical concerns to consider. The first is the thermal mixing in the water pool, and the other is the thermo-hydraulically induced mechanical loads acting on the structures of relevant systems. The two concerns are inter-related and can be well described only if the local behavior of the condensing steam jets and the resultant turbulent jet in a pool are well understood. In this paper, the DCC-related thermofluid dynamic features are discussed focusing on these two concerns. The fundamental characteristics of condensing steam jets are discussed, including the local behavior of condensing jets and the resultant turbulent jet, both of which importantly affect the macroscopic circulation in a pool. Then, a global analysis of thermal mixing in a pool from the viewpoints of the local hot spot and the thermal stratification are discussed with practical application to engineering design in mind.


Author(s):  
Woo Hyun Jung ◽  
Hyun Sun Park ◽  
Kiyofumi Moriyama ◽  
Moo Hwan Kim

The melt jet breakup phenomenon in a pre-flooded reactor cavity during a severe accident is related to the debris bed coolability. It is important to predict the jet breakup length for the evaluation of the debris bed coolability. A large volume of works on the jet breakup length have been performed. However, the consistency between experiments and correlations was difficult to achieve. Some data follow the Saito correlation (include Froude number in the correlation) and others follow the Epstein correlation (doesn’t include Froude number). The separation of the jet breakup length correlation along the water subcooling was reported based on the experimental data using the low melting temperature materials in our previous works. Since the previous experiments show an unclear jet shape before entering the water pool which could be an uncertainty factor, a slide gate system for a clear jet shape was additionally installed. Experiments were conducted with the similar condition of previous work and different initial condition of melt jet. With a clear jet shape, the jet breakup length in the subcooled water show different tendency following the Saito correlation. To figure out the effect of the entry condition of the melt jet, the jet diameter and the method of estimating the jet breakup length are revisited. Our previo0us experiments show large uncertainties on the jet diameter, leading to the large discrepancy of the dimensionless jet breakup length. Also, early broken jet core is reported in subcooled water cases. Thus, the uncertain characteristics of the jet breakup length analysis is discussed in this paper including the jet diameter and the method to estimate the jet breakup length.


Author(s):  
L. Ishay ◽  
U. Bieder ◽  
G. Ziskind ◽  
A. Rashkovan

Knowledge of the nuclear power plants (NPPs) containment atmosphere composition in the course of a severe accident is crucial for the effective design and positioning of the hydrogen explosion countermeasures. This composition strongly depends on containment flows which may include turbulent jet mixing in the presence of buoyancy, jet impingement onto the stratified layer, stable stratification layer erosion, steam condensation on the walls of the containment, condensation by emergency spray systems and other processes. Thus, in modeling of containment flows, it is essential to correctly predict these effects. In particular, a proper prediction of the turbulent jet behavior before it reaches the stably stratified layer is critical for the correct prediction of its mixing and impingement. Accordingly, validation study is presented for free neutral and buoyancy-affected turbulent jets, based on well-known experimental results from the literature. This study allows for the choice of a proper turbulence model to be applied for containment flow simulations. Furthermore, the jet behavior strongly depends on the issuing geometry. A comparative study of erosion process for the conditions similar to the ones of international benchmark exercise (IBE-3) is presented for different jet nozzle shapes.


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