Thermal-hydraulic investigation of the lead-bismuth alloy-cooled wire-wrapped fuel assembly with different pitch to diameter ratios and wire shapes

被引:0
作者
Feng, Xingyu [1 ,2 ]
Liang, Junming [2 ,3 ]
Wu, Tao [2 ]
Ju, Peng [2 ]
Xu, Xinhai [1 ,2 ]
机构
[1] CGN HIT Adv Nucl & New Energy Res Inst, Harbin 150001, Peoples R China
[2] Harbin Inst Technol, Sch Mech Engn & Automat, Shenzhen 518055, Peoples R China
[3] China Nucl Power Technol Res Inst, Shenzhen 518038, Peoples R China
关键词
Lead-bismuth; Fuel assembly; Wire-wrapped bundle; Pitch to diameter ratio; Subchannel; NUMERICAL SIMULATIONS; HEAT-TRANSFER; FLOW; BUNDLES;
D O I
10.1016/j.nucengdes.2024.113492
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This study develops a numerical model to investigate the effects of wire wrapping on the flow velocity and temperature distribution in a seven-rod fuel bundle cooling by lead-bismuth eutectic alloy. The enhanced cooling performance of the wire-wrapped rod is compared with the bare rod, and the oscillated local Nusselt numbers along the axial direction in the inter, corner and edge subchannels are analyzed. The Nusselt number oscillation is found strongly correlated with the area change in different subchannels induced by the wrapping wires. In order to reduce the temperature gradient along the axial direction and eliminate local hot spots, the impact of different pitch-to-diameter (P/D) ratios and wire geometries on the flow and heat transfer performances are examined while considering the fixed rated power of the rod bundles. For the central subchannel, a higher P/D ratio leads to significant fluctuation in transverse velocity, reduced temperature and increased Nusselt number. With P/D of 1.29, the average temperature of the central rod is reduced by 13.2 degrees C. The influence of P/D in the corner and edge subchannels are not significant due to wall effect. Among the wires with circular, rectangular and trapezoidal shapes, the trapezoidal wire shows the highest Nusselt number and the highest TSEF (Transverse Secondary Flow) value indicating the best heat transfer performance.
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页数:12
相关论文
共 26 条
[1]   Flow and convective heat transfer analysis using RANS for a wire-wrapped fuel assembly [J].
Ahmad, Imteyaz ;
Kim, Kwang-Yong .
JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, 2006, 20 (09) :1514-1524
[2]   Direct numerical simulation of turbulent forced and mixed convection of LBE in a bundle of heated rods with P/D=1.4 [J].
Angeli, D. ;
Fregni, A. ;
Stalio, E. .
NUCLEAR ENGINEERING AND DESIGN, 2019, 355
[3]  
[Anonymous], 2013, ANSYS FLUENT THEOR G
[4]   Numerical simulations for determination of minimum representative bundle size in wire wrapped tube bundles [J].
Brockmeyer, Landon ;
Carasik, Lane B. ;
Merzari, Elia ;
Hassan, Yassin .
NUCLEAR ENGINEERING AND DESIGN, 2017, 322 :577-590
[5]   Numerical investigation of thermal-hydraulic behaviors in a LBE-cooled 19-pin wire-wrapped rod bundle [J].
Chai, Xiang ;
Liu, Xiaojing ;
Xiong, Jinbiao ;
Cheng, Xu .
PROGRESS IN NUCLEAR ENERGY, 2020, 119
[6]   Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles [J].
Chen, S. K. ;
Todreas, N. E. ;
Nguyen, N. T. .
NUCLEAR ENGINEERING AND DESIGN, 2014, 267 :109-131
[7]   The blockage model of Upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles [J].
Chen, Y. M. ;
Chen, S. K. ;
Hassan, Y. .
NUCLEAR ENGINEERING AND DESIGN, 2022, 395
[8]  
FAN, 2018, A thesis submitted to University of Chinese Academy of Sciences in partial fulfillment of the requirement
[9]   Numerical investigation on flow-induced vibration and heat transfer of fuel rods in a small pitch-diameter ratio (P/D) channel [J].
Guo, Yonghui ;
Li, Xiaochang ;
Liu, Ju ;
Chen, Guangliang ;
Gao, Ye .
ANNALS OF NUCLEAR ENERGY, 2022, 171
[10]   Numerical analysis on the thermal hydraulic effect of wrapped wire spacer in a four rod fuel bundle [J].
Kiss, Attila ;
Mervay, Bence .
NUCLEAR ENGINEERING AND DESIGN, 2019, 342 :276-307