Numerical Investigation on Flow and Heat Transfer Characteristics of S-CO2 in Narrow Space Channel of PCHE Based on CFD Simulation

被引：0

作者：

Liu G. ^{[1
]}

Chen D. ^{[1
]}

Hu L. ^{[1
]}

Wang J. ^{[2
]}

机构：

[1] Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Chongqing University, Chongqing

[2] Institute of Nuclear Power of China, Chengdu

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2019年 / 40卷 / 03期

关键词：

Flow and heat transfer characteristics; Printed circuit heat exchangers (PCHE); Supercritical CO [!sub] 2[!/sub;

D O I：

10.13832/j.jnpe.2019.03.0012

中图分类号：

学科分类号：

摘要：

CFD method was used to investigate the thermal hydraulic characteristics of the printed circuit heat exchangers (PCHE) with zigzag channels, and the physical parameters of supercritical CO2 was calculated by combining the physical property fitting formulas and the user defined function (UDF ). In addition, the turbulent flow model was based on the SST k-ω model, and the CFD method was validated by the experimental data of friction coefficient and heat transfer coefficient. Simulation results show that in the zigzag channels of PCHE, the core accelerating area moves toward the outside wall at the bending point, and the separated flow area becomes narrow as the pressure drop decreases at the downstream part of the bending point. © 2019, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

引用

页码：12 / 16

页数：4

共 7 条

[1] Dostal, Vaclav, A supercritical carbon dioxide cycle for next generation nuclear reactors, Massachusetts Institute of Technology, 154, 3, pp. 265-282, (2004)
[2] Nikitin K., Kato Y., Ngo L., Printed circuit heat exchanger thermal-hydraulic performance in supercritical CO<sub>2</sub> experimental loop, International Journal of Refrigeration, 29, 5, pp. 807-814, (2006)
[3] Figley J., Sun X., Mylavarapu, Et al., Nu-merical study on thermal hydraulic performance of a printed circuit heat exchanger, Progress in Nuclear Energy, 68, pp. 89-96, (2013)
[4] Kim I.H., No H.C., Lee J.I., Et al., Thermal hydraulic performance analysis of the printed circuit heat exchanger using a helium test facility and CFD simulations, Nuclear Engineering & Design, 239, 11, pp. 2399-2408, (2009)
[5] Dong E.K., Kim M.H., Cha J.E., Et al., Numerical investigation on thermal-hydraulic performance of new printed circuit heat exchanger model, Nuclear Engineering & Design, 238, 12, pp. 3269-3276, (2008)
[6] Rabin B.H., Swank W.D., Wright R.N., Thermo-physical properties of Alloy 617 from 25℃ to 1000℃, Nuclear Engineering & Design, 262, pp. 72-80, (2013)
[7] Hu L., Chen D., Huang Y., Et al., Investigation on the performance of the supercritical Brayton cycle with CO<sub>2</sub>-based binary mixture as working fluid for an energy transportation system of a nuclear reactor, Energy, 89, pp. 874-886, (2015)

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