Abstract

Flow around Nuclear rod bundles' simulations based on RANS and LES method respectively

Highlights

  • High performance of rod bundles’ heat exchange is important to Pressurized Water Reactors’ fuel assemble design [1]

  • The experiment of 3x3 bundle flow for nuclear bundle design research was simulated by CFX

  • Mesh sensitive was checked during RANS simulation

Read more

Summary

Introduction

High performance of rod bundles’ heat exchange is important to Pressurized Water Reactors’ fuel assemble design [1]. CFD simulation is required to simulate the flow structure in order to understand and analysis the detail of the turbulence, mixing flow, velocity profile around rod bundles, as previously shown [2][3][7]. Whether the results of CFD simulation are accurate, it is still always in doubt. The most reliable validation is comparing simulation results with analytic solutions in theory or experiment data. The 3x3 rod bundle experiment simulated in this paper is the facility installed in Shanghai Jiao Tong University. The facility full of water is used to validate the nuclear lumped methods codes for Pressurized Water Reactors. The experiment data can be used to validate CFD methods.

Objectives
Methods
Conclusion

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 call

Disclaimer: 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.