Spacer grid is an important part of fuel assembly in reactor. The AFA-2G/3G spacer with mixing vane supports rod bundles well and enhances the heat transfer, but it has a complex structure and difficult processing. A novel spacer grid with the rectangular longitudinal vortex generators (RLVGs) is designed to improve thermal-hydraulic characteristics of fuel assembly. Based on the standard k-ε model with the enhanced wall treatment, a three-dimensional numerical simulation of the novel spacer grid in the channel of PWR fuel rods is presented. The effects of Reynolds number and attack angle are investigated. Numerical results show that the second flow generated by LVGs spreads to the downstream region of spacer grid and improves the heat transfer. The spacer grids with RLVGs with attack angles of 60° and 45° result in almost equal heat transfer performances. However, the spacer grid with RLVGs with attack angle of 60° brings about more pressure drop in comparison with that of the 45° case. The present research on new fuel assembly has certain potential value for the engineering design.
LIANG Haoyu
,
WU Junmei
. Numerical analysis of a novel spacer grid in rod bundles of PWR[J]. Journal of University of Chinese Academy of Sciences, 2018
, 35(2)
: 200
-208
.
DOI: 10.7523/j.issn.2095-6134.2018.02.008
[1] Holloway M V, Beasley D E, Conner M E. Single-phase convective heat transfer in rod bundles[J]. Nuclear Engineering and Design, 2008,238(4):848-858.
[2] Han S Y, Seo J S, Park M S, et al. Measurements of the flow characteristics of the lateral flow in the 6×6 rod bundles with Tandem Arrangement Vanes[J]. Nuclear Engineering and Design, 2009,239(12):2728-2736.
[3] Nematollahi M R, Nazifi M. Enhancement of heat transfer in a typical pressurized water reactor by different mixing vanes on spacer grids[J]. Energy Conversion and Management, 2008,49(7):1981-1988.
[4] Shin B S, Chang S H. CHF experiment and CFD analysis in a 2×3 rod bundle with mixing vane[J]. Nuclear Engineering and Design, 2009,239(5):899-912.
[5] Tóth S, Aszódi A. CFD analysis of flow field in a triangular rod bundle[J]. Nuclear Engineering and Design, 2010,240(2):352-363.
[6] Zhu X, Morooka S, Oka Y. Numerical investigation of grid spacer effect on heat transfer of supercritical water flows in a tight rod bundle[J]. International Journal of Thermal Sciences, 2014, 76(2):245-257.
[7] Tseng Y S, Ferng Y M, Lin C H. Investigating flow and heat transfer characteristics in a fuel bundle with split-vane pair grids by CFD methodology[J]. Annals of Nuclear Energy, 2014, 64(64):93-99.
[8] Bieder U, Falk F, Fauchet G. LES analysis of the flow in a simplified PWR assembly with mixing grid[J]. Progress in Nuclear Energy, 2014, 75(1):15-24.
[9] Podila K, Rao Y F, Krause M, et al. A CFD simulation of 5×5 rod bundles with split-type spacers[J]. Progress in Nuclear Energy, 2014, 70(1):167-175.
[10] Johnson T R, Joubert P N. The influence of vortex generators on the drag and heat transfer from a circular cylinder normal to an airstream[J]. Journal of Heat Transfer, 1969,91(1):91-99.
[11] Ahmed H E, Mohammed H A, Yusoff M Z. An overview on heat transfer augmentation using vortex generators and nanofluids:approaches and applications[J]. Renewable and Sustainable Energy Reviews, 2012,16(8):5951-5993.
[12] Wu J M, Tao W Q. Investigation on laminar convection heat transfer in fin-and-tube heat exchanger in aligned arrangement with longitudinal vortex generator from the viewpoint of field synergy principle[J]. Applied Thermal Engineering, 2007,27(14/15):2609-2617.
[13] Gandhir A, Hassan Y. RANS modeling for flow in nuclear fuel bundle in pressurized water reactors (PWR)[J]. Nuclear Engineering and Design, 2011,241(11):4404-4408.
[14] Liu C C, Ferng Y M, Shih C K. CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly[J]. Applied Thermal Engineering, 2012, 40(7):389-396.
[15] Agbodemegbe V Y, Cheng X, Akaho E H K, et al. An investigation of the effect of split-type mixing vane on extent of crossflow between subchannels through the fuel rod gaps[J]. Annals of Nuclear Energy, 2016,88:174-185.
[16] 陶文铨. 数值传热学[M].2版. 西安:西安交通大学出版社, 2001.