Abstract
In light water reactors each fuel rod is arranged in the shape of a square lattice with an interval of around 3 mm. Several spacers are installed on the surface of the fuel rod with arbitrary axial positions. Water flows vertically along fuel rods and is heated by those, and then many bubbles generate. In order to improve the thermal design procedure of the nuclear reactor core, it is needed to clarify velocity, pressure, temperature and void fraction distributions precisely based on the bubbly flow behavior in a vertical minichannel under the water-vapor two-phase flow condition. However, it is not easy to get those three-dimensional distributions by the experimental study. Then, large-scale two-phase flow simulations were performed to predict the three-dimensional bubby flow configurations in the simply simulated nuclear coolant channel. Regarding both mechanisms of the coalescence and fragmentation of bubbles the useful knowledge was obtained.Copyright © 2005 by ASME
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
