Numerical simulations for steam–water CCFL tests using the 1/3 scale rectangular channel simulating a PWR hot leg-Reference-Cited by-同舟云学术

Numerical simulations for steam–water CCFL tests using the 1/3 scale rectangular channel simulating a PWR hot leg

Published:2012-08 Issue: Volume:249 Page:14-23
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Utanohara Yoichi,Kinoshita Ikuo,Murase Michio,Lucas Dirk,Vallée Christophe,Tomiyama Akio

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference26 articles.

1. Countercurrent flow limitations in horizontal stratified flows of air and water. FZKA 7018;Gargallo Gallego;Forschungszentrum Karlsruhe,2004

2. One-dimensional drift-flux model and constitutive equations for relative motion between phases in various two-phase flow regimes. ANL-77-47;Ishii;Argonne National Laboratory,1977

3. Two-fluid model and hydro-dynamic constitutive relations;Ishii;Nucl. Eng. Des.,1984

4. Drift-flux parameters for upward gas flow in stagnant liquid;Kataoka;J. Nucl. Sci. Technol.,1987

5. Numerical simulation of countercurrent gas-liquid flow in a PWR hot leg under reflux cooling;Kinoshita;J. Nucl. Sci. Technol.,2010

Cited by 9 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Statistical characterization of the interfacial behavior captured by a novel image processing algorithm during the gas/liquid counter-current two-phase flow in a 1/3 scaled down of PWR hot leg;Nuclear Engineering and Design;2023-04

2. Experimental Investigations and Numerical Studies of Two-Phase Countercurrent Flow Limitation in a Pressurized Water Reactor: A Review;Energies;2023-02-02

3. An experimental study on the effect of liquid properties on the counter-current flow limitation (CCFL) during gas/liquid counter-current two-phase flow in a 1/30 scaled-down of Pressurized Water Reactor (PWR) hot leg geometry;Nuclear Engineering and Design;2022-12

4. TOPFLOW pressure chamber – Versatile techniques to simplify design and instrumentation of thermal fluid dynamic experiments at high pressure;Nuclear Engineering and Design;2021-02

5. Characterization and prediction of flow-conditions in the hot-leg of PWR during loss of coolant accident;Nuclear Engineering and Design;2020-04