Numerically simulating the thermal-hydraulic characteristics within the fuel rod bundle using CFD methodology
Creators
- 1. Institute of Nuclear Engineering and Science, National Tsing Hua University, 101, Section 2, Kuang-Fu Road, Hsingchu 30013, 325 Taiwan (China)
Description
With the dramatic progress in the computer processing power, computational fluid dynamics (CFD) methodology can be applied in investigating the detailed knowledge of thermal-hydraulic characteristics in the rod bundle, especially with the spacer grid. These localized information, including flow, turbulence, and heat transfer characteristics, etc., can assist in the design and the improvement of rod bundles for nuclear power plants. In this paper, a three-dimensional (3D) CFD model with the Reynolds stresses turbulence model is proposed to simulate these characteristics within the rod bundle and subsequently to investigate the effects of different types of grid on the turbulent mixing and heat transfer enhancement. Two types of grid designs are used herein, including the standard grid and split-vane pair one, respectively. Based on the CFD simulations, the secondary flow can be reasonably captured in the rod bundle with the grid. The split-vane pair grid would enhance both the flow mixing and the heat transfer capability more than the standard grid does, as clearly shown in the simulation results. In addition, compared with the results of experiment and correlation, the present predicted result for the Nusselt (Nu) number distribution downstream the grid shows reasonable agreement for the standard grid design. However, there is discrepancy in the decay trend of Nu number between the prediction and measurement for the split-vane pair gird. This would be improved by adopting the finer mesh (y+ < 1) simulation and Low-Reynolds form turbulence model, which is our future research work.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2010.05.021Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2010.05.021;
- PII
- S0029-5493(10)00346-8;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 240
- Journal Issue
- 10
- Journal Page Range
- p. 3078-3086
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 4. international topical meeting on high temperature reactor technology
- Acronym
- HTR 2008
- Dates
- 28 Sep - 1 Oct 2008
- Place
- Washington, DC (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42013327
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DESIGN; FLUID MECHANICS; FUEL ELEMENT CLUSTERS; FUEL RODS; HEAT TRANSFER; NUCLEAR POWER PLANTS; REYNOLDS NUMBER; SPACERS; STRESSES; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TURBULENCE
- Descriptors DEC
- DIMENSIONLESS NUMBERS; ENERGY TRANSFER; FLUID MECHANICS; FUEL ASSEMBLIES; FUEL ELEMENTS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; SIMULATION; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.