CFD Investigation on Flow and Heat Transfer Characteristics of Fuel Assembly for VVER Reactor

Wang Xiong; Du Daiquan; Zeng Xiaokang; Yang Xiaoqiang; Zan Yuanfeng

doi:10.13832/j.jnpe.2018.03.0006

Volume 39 Issue 3

Jul. 2018

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2018 > 39(3): 6-9

Wang Xiong, Du Daiquan, Zeng Xiaokang, Yang Xiaoqiang, Zan Yuanfeng. CFD Investigation on Flow and Heat Transfer Characteristics of Fuel Assembly for VVER Reactor[J]. Nuclear Power Engineering, 2018, 39(3): 6-9. doi: 10.13832/j.jnpe.2018.03.0006

Citation:

Wang Xiong, Du Daiquan, Zeng Xiaokang, Yang Xiaoqiang, Zan Yuanfeng. CFD Investigation on Flow and Heat Transfer Characteristics of Fuel Assembly for VVER Reactor[J]. Nuclear Power Engineering, 2018, 39(3): 6-9. doi: 10.13832/j.jnpe.2018.03.0006

Citation:

PDF( 768 KB)

CFD Investigation on Flow and Heat Transfer Characteristics of Fuel Assembly for VVER Reactor

doi: 10.13832/j.jnpe.2018.03.0006

1. Nuclear Power Institute of China, Chengdu, 610041, China;
2. Jiangsu Nuclear Power Corporation of CNNC, Lianyungang, Jiangsu, 222042, China

Received Date: 2018-01-16
Rev Recd Date: 2018-05-04

Abstract

Abstract

The flow and heat transfer characteristics of AFA fuel assembly for VVER reactors have been investigated using computational fluid dynamics（CFD） simulation. The flow field, pressure drop and temperature distribution of the coolant in AFA under normal regime have been calculated. The results show that the pressure drop of the spacer grid of AFA is lower than that of the grid having mixing vane. The stagnation zone of coolant appears around the rim of the spacer grid and causes higher temperature in the periphery region of AFA. The power ratio of the circumferential pin around instrumental tube（K_c） with different values has a great effect on the measured temperature of the coolant at FA outlet. The results can be referred in the setting of temperature warning value（ΔT_t） for the reactor core during the operation of nuclear power plants.
- Pressure drop,
- Temperature distribution,
- Computational fluid dynamics（CFD）

FullText(HTML)

References(0)

References

Relative Articles

[1]	Zhang Tao, Han Wenbin, Shen Pengfei, Huang Shanfang, Wang Kan. Neutronic and Thermal-Hydraulic Performance Analysis of Helical Cruciform Fuel Rods[J]. Nuclear Power Engineering, 2023, 44(S1): 69-74. doi: 10.13832/j.jnpe.2023.S1.0069
[2]	Feng Linna, Chen Jie, Su Min, Pu Zengping. Study On Hydraulic Properties of Bottom Nozzle of CF3 Fuel Assembly[J]. Nuclear Power Engineering, 2022, 43(S2): 208-212. doi: 10.13832/j.jnpe.2022.S2.0208
[3]	Wang Da, Niu Fenglei, Liang Ruixian, Zhuo Weiqian, LiuJun. Experimental Study on Effect of Containment Debris on Pressure Drops of PWR Fuel Assembly after LOCA[J]. Nuclear Power Engineering, 2019, 40(6): 24-29. doi: 10.13832/j.jnpe.2019.06.0024
[4]	Peng Yinbo, Zhang Yajun, Jia Haijun, Wu Lei, Liu Yang. Investigation on Effect of Cool/Hot Core Deviation on Natural Circulation Capacity in Natural Circulation Loop[J]. Nuclear Power Engineering, 2018, 39(1): 38-42. doi: 10.13832/j.jnpe.2018.01.0038
[5]	Tang Hong. Numerical Simulation of Flow in 3×3 Rod Bundle in Vertical and Inclined Conditions[J]. Nuclear Power Engineering, 2017, 38(S1): 45-48. doi: 10.13832/j.jnpe.2017.S1.0045
[6]	Zhou Huihui, Xie Tianzhou, Xu Jianjun, Chen Bingde, Zhang Bin. Two-Phase Pressure Drop Characteristics in Circular Tube under Rolling Motion[J]. Nuclear Power Engineering, 2017, 38(2): 28-31. doi: 10.13832/j.jnpe.2017.02.0028
[7]	Han Bin, Yang Baowen, Zhang Hui, ChA Yudong, Peng Cheng. Analysis of Empirical Pressure Drop Correlations and CFD Numerical Study on Spacer Grid[J]. Nuclear Power Engineering, 2017, 38(2): 169-174. doi: 10.13832/j.jnpe.2017.02.0169
[8]	Li Tongye, Wang Hui, Chen Jianhua, Pan Xiaoqiang. Coupled Numerical Simulation of Nuclear Fuel Particles Fluidization and CVD Reaction in Deposition Chamber for Niobium Coating[J]. Nuclear Power Engineering, 2016, 37(1): 52-56. doi: 10.13832/j.jnpe.2016.01.0052
[9]	Wang Yu, Chen Zhihui, Hao Chengming, Sun Yan, Huang Wei. Study on Leak Detection for Passive Residual Heat Remove System[J]. Nuclear Power Engineering, 2016, 37(1): 86-90. doi: 10.13832/j.jnpe.2016.01.0086
[10]	Li Yong, Zhu Haiyan, Wen Bo, Zhao Erlei, Zan Yuanfeng, Zhuo Wenbin, Li Pengzhou. Scale Analysis of Hydraulic Test of Tube Support Plate in Steam Generator Based on Computational Fluid Dynamics[J]. Nuclear Power Engineering, 2016, 37(4): 39-43. doi: 10.13832/j.jnpe.2016.04.0039
[11]	He Gening, He Jingsong, Li Donghui, Wu Ge, Huo Meng. Flow Analysis and Structure Optimization of Electric Heating Tank of Steam Generator Secondary Side Pre-Service Hydrostatic Test System[J]. Nuclear Power Engineering, 2015, 36(S2): 46-49. doi: 10.13832/j.jnpe.2015.S2.0046
[12]	Zhang Huang, Bo Hanliang, Chen Feng. Numerical Simulation of Separation Efficiency and Pressure Drop of AP1000 Swirl-Vane Moisture Separator[J]. Nuclear Power Engineering, 2015, 36(5): 75-79. doi: 10.13832/j.jnpe.2015.05.0075
[13]	Sun Yan, Liang Tiebo, Chen Zhihui, Zhao Jing, Zhang Yulong. 3-D Steady Analysis of Flow in CRDM Sewerage System[J]. Nuclear Power Engineering, 2014, 35(6): 144-147. doi: 10.13832/j.jnpe.2014.06.0144
[14]	Cao Nian, Zhang Yan, Wen Yan, JiA Chuan, Xiong Wanyu. Evaluation and Optimization of Ventilation Systems of Control Rods in Nuclear Power Plants[J]. Nuclear Power Engineering, 2014, 35(5): 97-100,137. doi: 10.13832/j.jnpe.2014.05.0097
[15]	Zhang Hongliang, Liu Haipeng, Fang Caishun, Lu Chuan. Optimization Design of Reactor Lower Plenum[J]. Nuclear Power Engineering, 2014, 35(3): 59-63. doi: 10.13832/j.jnpe.2014.03.0059
[16]	FENG Zhipeng, ZANG Fenggang, ZHANG Yixiong, YE Xianhui. Flow Characteristic Analysis of Flow Induced Heat Exchanger Tube Vibration[J]. Nuclear Power Engineering, 2014, 35(2): 71-75.
[17]	ZENG Xiao-kang, LI Yong-liang, YAN Xiao, XIAO Ze-jun, HUANG Yan-ping. Application of CFD Methods in Research of SCWR Thermo-Hydraulics[J]. Nuclear Power Engineering, 2013, 34(1): 114-120.
[18]	LU Chuan, ZHANG Yong, LU Jian-chao, DONG Hua-ping. Analysis of Flow Behavior of Coolant in Natural Circulation Reactor Based on Computational Fluid Dynamics[J]. Nuclear Power Engineering, 2012, 33(S1): 111-114,118.
[19]	CHEN De-qi, REN Song, PAN Liang-ming, YUAN De-wen, LIU Bin. Characteristics of Effect of Vapor Bubble Behavior on Pressure Drop in Vertical Rectangular Narrow Channel[J]. Nuclear Power Engineering, 2012, 33(S1): 75-79,84.
[20]	JIA Hui, TAN Sichao, GAO Puzhen, YAN Changqi, HUANG Yanping. Experimental Study on Friction Pressure Drop Characteristics of Simple Harmonic Pulse Flow Pole Point[J]. Nuclear Power Engineering, 2011, 32(3): 102-105,126.

Supplements(0)

Cited By

Cited by

Periodical cited type(3)

1.	崔怡然，杨忠波，刘然超，邓传东，王晓敏，邱军，徐春容. Zr-Sn-Nb合金带材力学性能各向异性研究. 核动力工程. 2023(S1): 131-136 . 本站查看
2.	李伟才，刘鹏亮，王从政，郭严. 压水堆燃料辐照后燃料棒棒间距数据机器视觉测量方法研究. 核动力工程. 2022(04): 53-59 . 本站查看
3.	朱亮宇，周涛，秦雪猛，丁锡嘉，张家磊. 不同尺寸管道中细颗粒的沉积运动规律研究. 核科学与工程. 2019(05): 695-700 .