Numerical Simulation of Flow Field in Cooling Tower of Passive Residual Heat Removal System of HTGR

LI Xiaowei; ZHANG Li; WU Xinxin; HE Shuyan

Volume 32 Issue 3

Mar. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2011 > 32(3): 58-62,72

LI Xiaowei, ZHANG Li, WU Xinxin, HE Shuyan. Numerical Simulation of Flow Field in Cooling Tower of Passive Residual Heat Removal System of HTGR[J]. Nuclear Power Engineering, 2011, 32(3): 58-62,72.

Citation:

LI Xiaowei, ZHANG Li, WU Xinxin, HE Shuyan. Numerical Simulation of Flow Field in Cooling Tower of Passive Residual Heat Removal System of HTGR[J]. Nuclear Power Engineering, 2011, 32(3): 58-62,72.

LI Xiaowei, ZHANG Li, WU Xinxin, HE Shuyan. Numerical Simulation of Flow Field in Cooling Tower of Passive Residual Heat Removal System of HTGR[J]. Nuclear Power Engineering, 2011, 32(3): 58-62,72.

Citation:

LI Xiaowei, ZHANG Li, WU Xinxin, HE Shuyan. Numerical Simulation of Flow Field in Cooling Tower of Passive Residual Heat Removal System of HTGR[J]. Nuclear Power Engineering, 2011, 32(3): 58-62,72.

PDF( 673 KB)

Numerical Simulation of Flow Field in Cooling Tower of Passive Residual Heat Removal System of HTGR

Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China

Received Date: 2010-01-19
Available Online: 2025-03-08

Abstract

Abstract

Environmental wind will influence the working conditions of natural convection cooling tower.The velocity and temperature fields in the natural convection cooling tower of the HTGR residual heat removal system at different environmental wind velocities were numerically simulated.The results show that,if there is no wind baffle,the flow in the cooling tower is blocked when environmental wind velocity is higher than 6 m/s,residual heat can hardly be removed,and when wind velocity is higher than 9 m/s,the air even flow downwards in the tower,so wind baffle is very necessary.With the wind baffle installed,the cooling tower works well at the wind speed even higher than 9 m/s.The optimum baffle size and positions are also analyzed.
- High temperature gas-cooled reactor,
- Residual heat removal,
- Numerical simulation,
- Natural convection,
- Porous media

FullText(HTML)

References(0)

References

Relative Articles

[1]	He Tengjiao, Han Fei, Li Songwei, Zhang Shuang, Wu Bin, Cheng Xianyan, Yuan Peng. Design and Application of a Collaborative Design Platform for Reactor Numerical Calculation[J]. Nuclear Power Engineering, 2024, 45(S2): 133-136. doi: 10.13832/j.jnpe.2024.S2.0133
[2]	Liu Yapeng, Zhang Dalin, Chen Yutong, Zhou Lei, Tian Wenxi, Qiu Suizheng, Su Guanghui. Numerical Simulation of the Natural Circulation Test of PHENIX Reactor by ACENA[J]. Nuclear Power Engineering, 2024, 45(5): 121-127. doi: 10.13832/j.jnpe.2024.05.0121
[3]	Wang Zhengquan, Yang Ting, Wen Qinglong, Xu Shijia, Chen Kang, Cheng Cheng, Tang Qionghui. Numerical Study on Heat Transfer Characteristics of a Scaled Model for Horizontal Dry Storage System of Spent Fuel[J]. Nuclear Power Engineering, 2024, 45(3): 68-75. doi: 10.13832/j.jnpe.2024.03.0068
[4]	Chen Zehan, Chen Xingwei, Dai Ye, Zou Yang. Study on the Effect of Inclination Angle on the Natural Convection of Molten Salt in Heat Pipe Cooled Molten Salt Reactor Core[J]. Nuclear Power Engineering, 2023, 44(4): 79-87. doi: 10.13832/j.jnpe.2023.04.0079
[5]	Tang Xiangdong, Li Wei. Numerical Simulation Research on Three-dimensional Temperature Field and Flow Field at the Top of Reactor under Natural Convection Conditions[J]. Nuclear Power Engineering, 2023, 44(S2): 44-49. doi: 10.13832/j.jnpe.2023.S2.0044
[6]	Ding Xueyou, Chen Zhiqiang, Wen Qinglong, Ruan Shenhui, Qiao Pengrui. Numerical Investigation on Thermal Hydraulics of Helical Coil Tube Once Through Steam Generator for LBE Fast Reactor[J]. Nuclear Power Engineering, 2021, 42(4): 21-26. doi: 10.13832/j.jnpe.2021.04.0021
[7]	Long Teng, Zhang Guihe, Gao Chen, Liu Pan, Deng Xiaoyun, Jin Ting, Xiong Guangming. Prediction of Natural Convection Characteristics of Spent Fuel Vessel with Multi-Fluid Domains and High Temperature Difference Based on Non-Boussinesq Model[J]. Nuclear Power Engineering, 2021, 42(3): 18-25. doi: 10.13832/j.jnpe.2021.03.0018
[8]	Liu Yiqun, Zhang Xiaoying, Wang Biao, Xu Junying, Zhang Lei, Zhang Huiyong, Zhan Dekui. Numerical Study on Core Transient Heat Transfer and Melt Process after LOCA[J]. Nuclear Power Engineering, 2018, 39(1): 122-127. doi: 10.13832/j.jnpe.2018.01.0122
[9]	Yan Xiao, Hu Qiang, Huang Shanfang, Yu Junchong, Li Yang. Analysis of Natural Circulation Flow Characteristics under External Vessel Cooling of In-Vessel Retention[J]. Nuclear Power Engineering, 2017, 38(4): 172-177. doi: 10.13832/j.jnpe.2017.04.0172
[10]	Liu Yang, Wang Jun. Heat Transfer Simulation of Fuel Transport Cask for High Temperature Gas Cooled Reactor[J]. Nuclear Power Engineering, 2017, 38(5): 160-163. doi: 10.13832/j.jnpe.2017.05.0160
[11]	Lai Jianyong, Shen Yunhai, Wang Baoping, Yu Xiaoquan, Sui Haiming, Zhu Li, Yu Fei. Research on Passive Residual Heat Removal System of SG Secondary Side of Underground Nuclear Power Plants[J]. Nuclear Power Engineering, 2016, 37(5): 135-137. doi: 10.13832/j.jnpe.2016.05.0135
[12]	Ge Jian, Cong Tenglong, Zhang Wenwen, Tian Wenxi, Qiu Suizheng, Su Guanghui. Numerical Research for Passive Residual Heat Removal Heat Exchanger under Natural Convection Condition[J]. Nuclear Power Engineering, 2016, 37(1): 129-132. doi: 10.13832/j.jnpe.2016.01.0129
[13]	ZHANG Sheng, GU Hanyang, CHEN Yuqing, ZHOU Xiaojia, LIU Gang. Experimental and Numerical Investigations of Natural Convection in a Vertical Annulus[J]. Nuclear Power Engineering, 2015, 36(1): 14-17. doi: 10.13832/j.jnpe.2015.01.0014
[14]	Li Hua, Chen Ping, Qiu Suizheng, Su Guanghui, Tian Wenxi, Li Yun, Su Min. Experimental Study on Two-Phase Flow Characteristics in Pebble-Bed Porous Media Channel[J]. Nuclear Power Engineering, 2014, 35(6): 21-25. doi: 10.13832/j.jnpe.2014.06.0021
[15]	Yuan Xiao, Peng Minjun, XiA Genglei, Liu Xinkai. Design and Simulation of Passive Residual Heat Removal System for Nuclear Power Plants[J]. Nuclear Power Engineering, 2014, 35(5): 53-56. doi: 10.13832/j.jnpe.2014.05.0053
[16]	ZHANG Xiao-ning, SUN Zhong-ning, MENG Xian-ke, XU Guang-zhan. Effect of Variable Viscosity on Flow Resistance Characteristics of Porous Channel with Internal Heat Source[J]. Nuclear Power Engineering, 2013, 34(4): 23-26.
[17]	ZHANG Zhen, YAN Xiao, XIAO Ze-jun. Experimental Research on Single Phase Flow and Convection Heat Transfer in Heat-Generating Porous Media[J]. Nuclear Power Engineering, 2012, 33(S1): 1-4.
[18]	YANG Jian, YAN Xiao, CENG Min, WANG Qiuwang. Experimental Study on Forced Convective Heat Transfer in Structured Packed Porous Media with Spherical or Ellipsoidal Particles[J]. Nuclear Power Engineering, 2012, 33(S1): 85-89.
[19]	TIAN Lin, HUANG Zi-peng, WANG Gang. Numerical Investigation of Local Thermal Non-Equilibrium Natural Convection in a Square Enclosure with Heat Generating Porous Medium[J]. Nuclear Power Engineering, 2012, 33(S1): 95-99,103.
[20]	ZHOU Xu-hua, LI Fu, CAI Qi, HAN Ren-yu. Calculation and Characteristic Analysis of Ex-Core Detector Spatial Response Function for High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2011, 32(6): 1-6.