Large eddy simulation of turbulent flow in the rod bundle with different spacer grids
Creators
- 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China (NPIC), Chengdu (China)
- 2. Nuclear Power Design and Research Sub-Institute, Nuclear Power Institute of China (NPIC), Chengdu (China)
Description
Large eddy simulation (LES) of the swirling flow in the rod bundle subchannels with spacer grids are presented. According to the rod bundle flow benchmark experiment, the 5×5 rod bundle with a split-type spacer grid is simulated by this transient simulation with a fine hybrid mesh. Mean velocity components, RMS (root mean square) velocity components and turbulent kinetic energy profiles at different locations downstream the mixing vanes are compared between the experiment and simulation results. LES results can reproduce the mixing turbulent flow velocity field well. We also have studied the influence of the mixing vanes' bending degree on the subchannel flow structures by using LES to simulate the 3×3 rod bundle with the typical PWR spacer grid. The mixing vanes' bending degree is modified to 35deg and 40deg based on the original spacer grid, whose mixing vanes' bending degree is 30deg. The larger bending degree produces a stronger mean coolant mixing effect, while larger pressure loss and fluctuation come together with this effect. The increased pressure loss would generate additional flow resistance, and larger fluctuation of coolant flow would make the mixing effect unstable, as well as would cause flow-induced vibration and grid-to-rod fretting phenomena. The LES method is a viable tool to optimize the spacer grid design and provide transient flow field data for mechanical analysis. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 23th international conference on nuclear engineering (ICONE-23)
- Imprint Pagination
- [3737 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- 23. international conference on nuclear engineering
- Acronym
- ICONE-23
- Dates
- 17-21 May 2015
- Place
- Chiba (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48046452
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENDING; COOLANTS; CRITICAL HEAT FLUX; FLUID MECHANICS; FUEL ELEMENT CLUSTERS; LARGE-EDDY SIMULATION; LASER DOPPLER ANEMOMETERS; PWR TYPE REACTORS; REACTOR KINETICS; SPACERS; TURBULENT FLOW; VORTEX FLOW
- Descriptors DEC
- ANEMOMETERS; COMPUTERIZED SIMULATION; DEFORMATION; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; HEAT FLUX; KINETICS; MEASURING INSTRUMENTS; MECHANICS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as DVD-ROM Data in PDF format. Folder Name: FullPaper; Paper ID: ICONE23-1150.pdf; 12 refs., 12 figs., 1 tab.