Modelling Analysis of Non-uniform Flow and Heat Transfer in Parallel Rectangular Channels under Flow Blockage Condition

Chen Jiayue; Wang Zefeng; Wang Xiaoyu; Chen Huandong

doi:10.13832/j.jnpe.2023.S1.0001

Volume 44 Issue S1

Jun. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(S1): 1-8

Chen Jiayue, Wang Zefeng, Wang Xiaoyu, Chen Huandong. Modelling Analysis of Non-uniform Flow and Heat Transfer in Parallel Rectangular Channels under Flow Blockage Condition[J]. Nuclear Power Engineering, 2023, 44(S1): 1-8. doi: 10.13832/j.jnpe.2023.S1.0001

Citation:

Chen Jiayue, Wang Zefeng, Wang Xiaoyu, Chen Huandong. Modelling Analysis of Non-uniform Flow and Heat Transfer in Parallel Rectangular Channels under Flow Blockage Condition[J]. Nuclear Power Engineering, 2023, 44(S1): 1-8. doi: 10.13832/j.jnpe.2023.S1.0001

Citation:

Chen Jiayue, Wang Zefeng, Wang Xiaoyu, Chen Huandong. Modelling Analysis of Non-uniform Flow and Heat Transfer in Parallel Rectangular Channels under Flow Blockage Condition[J]. Nuclear Power Engineering, 2023, 44(S1): 1-8. doi: 10.13832/j.jnpe.2023.S1.0001

PDF( 7177 KB)

Modelling Analysis of Non-uniform Flow and Heat Transfer in Parallel Rectangular Channels under Flow Blockage Condition

doi: 10.13832/j.jnpe.2023.S1.0001

1.
Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai, Guangdong, 519082, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-03-09
Rev Recd Date: 2023-05-11
Publish Date: 2023-06-15

Abstract

Abstract

In order to establish the non-uniform flow and heat transfer modelling method for parallel rectangular channels, and provide a new modelling method and tool for the safety analysis of plate-type fuel, one dimensional two-fluid model coupled with two-dimensional heat conduction of fuel are used to develop a thermal-hydraulic transient analysis code for non-uniform flow and heat transfer simulation under flow blockage condition. The flow distribution and fuel temperature field under different blockage conditions are obtained by numerical simulation, and the two-dimensional heat conduction effect of the fuel under four different power distributions is also studied. The simulation results show that the flow and heat transfer in parallel channels would redistribute after blockage. And the two-dimensional heat conduction model predictes a more uniform temperature profile of fuel plate cross-section. Thus, the thermal-hydraulic transient analysis code developed in this paper can be unsed to simulate the non-uniform flow and heat transfer for the plate-type fuel.
- Plate type fuel,
- Flow blockage,
- Rectangular channel,
- Parallel channels

FullText(HTML)

References(13)

References

[1]	HAMIDOUCHE T, BOUSBIA-SALAH A, ADORNI M, et al. Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code[J]. Annals of Nuclear Energy, 2004, 31(12): 1385-1402. doi: 10.1016/j.anucene.2004.03.008
[2]	李健全,陈晓明,李金才. 板状燃料堆芯流道阻塞事故分析[J]. 原子能科学技术,2002, 36(1): 76-79.
[3]	AGHAIE M, ZOLFAGHARI A, MINUCHEHR A, et al. Transient analysis of break below the grid in Tehran research reactor using the newly enhanced COBRA-EN code[J]. Annals of Nuclear Energy, 2012, 49: 1-11. doi: 10.1016/j.anucene.2012.06.017
[4]	ALMACHI J C, SÁNCHEZ-ESPINOZA V, IMKE U. Extension and validation of the SubChanFlow code for the thermo-hydraulic analysis of MTR cores with plate-type fuel assemblies[J]. Nuclear Engineering and Design, 2021, 379: 111221. doi: 10.1016/j.nucengdes.2021.111221
[5]	OBENCHAIN C F. PARET: a program for the analysis of reactor transients: IDO-17282[R]. Idaho Falls: Phillips Petroleum Co. , 1969.
[6]	HAINOUN A, GHAZI N, ALHABIT F. Simulation of LOFA and RIA for the IEA-R1 research reactor using the Code MERSAT[J]. Annals of Nuclear Energy, 2008, 35(11): 2093-2104. doi: 10.1016/j.anucene.2008.05.013
[7]	LU Q, QIU S Z, SU G H. Development of a thermal-hydraulic analysis code for research reactors with plate fuels[J]. Annals of Nuclear Energy, 2009, 36(4): 433-447. doi: 10.1016/j.anucene.2008.11.038
[8]	刘伟,张勇,蒋孝蔚,等. 板型燃料元件反应堆瞬态热工水力分析程序的开发与验证[J]. 核动力工程,2019, 40(5): 18-22. doi: 10.13832/j.jnpe.2019.05.0018
[9]	Idaho National Laboratory. RELAP-3D code manual Volume I: Models and Correlations: INEEL-EXT-98-00834, Revision 4.0[R]. USA Idaho: Idaho National Laboratory, 2012.
[10]	陈佳跃, 陈焕栋, 张小英, 等. 两流体模型求解算法及其对若干激波问题的模拟[C]//重庆: 国家能源核电软件重点实验室年会, 2018.
[11]	MA J, LI L J, HUANG Y P, et al. Experimental studies on single-phase flow and heat transfer in a narrow rectangular channel[J]. Nuclear Engineering and Design, 2011, 241(8): 2865-2873. doi: 10.1016/j.nucengdes.2011.04.047
[12]	SUDO Y, USUI T, KAMINAGA M. Heat transfer characteristics in narrow vertical rectangular channels heated from both sides[J]. JSME International Journal. Ser. 2, Fluids Engineering, Heat Transfer, Power, Combustion, Thermophysical Properties, 1990, 33(4): 743-748. doi: 10.1299/jsmeb1988.33.4_743
[13]	GHIONE A, NOEL B, VINAI P, et al. Assessment of thermal—hydraulic correlations for narrow rectangular channels with high heat flux and coolant velocity[J]. International Journal of Heat and Mass Transfer, 2016, 99: 344-356. doi: 10.1016/j.ijheatmasstransfer.2016.03.099