Affiliation:
1. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH , Boltzmannstrasse 14, 85748 Garching at Munich , Germany
Abstract
Abstract
Spacer grids with mixing vanes have complex geometry and are used to support the fuel rods in nuclear fuel assemblies as well as to improve heat transfer by generating turbulence downstream of the spacer grid in the cores of the pressurized water reactors. To validate the CFD code OpenFOAM for relevant spacer grid geometries, numerical analyses on the OECD/NEA MATiS-H benchmark were performed. The flow behind two different types of spacer grid designs was analysed: split- and swirl-type. Initially, an appropriate inlet velocity profile was generated. In a next step, Computer-Aided Design models of the spacer grids were prepared and then meshed using ANSYS Mesher 19.2. Transient URANS simulations were performed with the k-ω-SST turbulence model and the results were compared with data. Good agreement was obtained for the mean velocity profile and the vorticity in the swirl-type configuration, while the numerical results slightly overestimated the transverse velocity profile at some measurements locations of the split-type configuration.
The content of this article was initially presented at the 33rd German CFD Network of Competence Meeting, held on March 22–23 at GRS in Garching, Germany.
Subject
Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation
Reference15 articles.
1. Baglietto, E. and Ninokata, H. (2005). A turbulence model study for simulating flow inside tight lattice rod bundles. Nucl. Eng. Des. 235: 773–784, https://doi.org/10.1016/j.nucengdes.2004.10.007.
2. Buchholz, S., Palazzo, S., Papukchiev, A., and Scheuerer, M. (2016). Development and validation of three-dimensional CFD techniques for reactor safety applications. Final report (GRS–375). Germany.
3. Cinosi, N., Walker, S.P., Bluck, M.J., and Issa, R. (2014). CFD simulation of turbulent flow in a rod bundle with spacer grids (MATIS-H) using STAR-CCM+. Nucl. Eng. Des. 279: 37–49, https://doi.org/10.1016/j.nucengdes.2014.06.019.
4. Dominguez-Ontiveros, E.E. and Hassan, Y.A. (2009). Non-intrusive experimental investigation of flow behavior inside a 5×5 rod bundle with spacer grids using PIV and MIR. Nucl. Eng. Des. 239: 888–898, https://doi.org/10.1016/j.nucengdes.2009.01.009.
5. Frank, T., Jain, S., Matyushenko, A.A., and Garbaruk, A.V. (2012). The OECD/NEA MATIS-H benchmark—CFD analysis of water flow through a 5x5 rod bundle with spacer grids using ANSYS FLUENT and ANSYS CFX. Page 12 In: Conference on experimental validation and application of CFD and CMFD codes in nuclear reactor technology, OECD/NEA and IAEA Workshop.
Cited by
1 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