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Numerical simulation on heat convection of supercriticalwater flow in axisymmetric channel(PDF)

《南京理工大学学报》（自然科学版）[ISSN:1005-9830/CN:32-1397/N]

Issue:
2019年03期
Page:
337-344
Research Field:
Publishing date:

Info

Title:
Numerical simulation on heat convection of supercriticalwater flow in axisymmetric channel
Author(s):
Wang Linglong; Hu Dinghua; Lv Xujian
School of Energy and Power Engineering,Nanjing University of Science and Technology,Nanjing 210094,China
Keywords:
axisymmetric channels;  supercritical water;  light water reactors;  heat flux densities;  heat convection enhancement;  heat convection deterioration
PACS:
TP319.56
DOI:
-
Abstract:
The heat convection process between the supercritical water and pipe wall in a vertical annular channel is numerically simulated by Fluent to investigate the flow and thermal characteristics of the working fluid in cooling channels of a high performance light water reactor. The influence of different grid numbers,the height between the adjacent grid and the wall and turbulence models on the accuracy of numerical simulation is evaluated by the comparison between the numerical and the experimental data. Five turbulent models are compared by computation. The core heat convection simulation is carried out for three different heat flux densities. The simulation results show that the accuracy of the forecast improves with increasing grid number and decreasing height between the adjacent grid and the wall,and the accuracy of the forecast has nothing to do with the height between the adjacent grid and the wall less than 0.07; the standard k-ω model and the SST k-ω model can predict the heat convection deterioration of the core either,and the SST k-ω model shows better accuracy; the significant change of physical properties in the near wall area is the main reason for heat convection enhancement or heat convection deterioration.

References:

[1] Schatte G A,Kohlhepp A,Wieland C,et al. Development of a new empirical correlation for the prediction of the onset of the deterioration of heat transfer to supercritical water in vertical tubes[J]. International Journal of Heat and Mass Transfer,2017,113:1332-1332.
[2]Schulenberg T,Leung L K H,Oka Y. Review of R&D for supercritical water cooled reactors[J]. Progress in Nuclear Energy,2014,77:282-299.
[3]Tashakor S,Salehi A A,Jahanfarnia G,et al. Thermal-hydraulic analysis of HPLWR fuel assembly cluster[J]. Journal of Supercritical Fluids,2013,77:91-99.
[4]丛凯峰. 螺旋盘管内超临界流体湍流换热数值模拟[D]. 哈尔滨:哈尔滨工业大学能源工程与科学学院,2017.
[5]姚强. 基于OpenFOAM的超临界压力流动传热数值模拟[D]. 大连:大连理工大学航空航天学院,2017.
[6]于水清,李会雄. 质量流速的变化对超临界水流动传热特性的影响[J]. 内蒙古煤炭经济,2017,17:140,145.
Yu Shuiqing,Li Huixiong. Influence of mass flow rate of supercritical water on heat transfer characteristics[J]. Inner Mongolia Coal Economy,2017,17:140,145.
[7]朱诚,郑林. 基于格子Boltzmann方法的热毛细对流数值模拟研究[J]. 南京理工大学学报,2017,41(6):773-778.
Zhu Cheng,Zheng Lin. Numerical simulation of thermocapillary convection based on lattice Boltzmann method[J]. Journal of Nanjing University of Science and Technology,2017,41(6):773-778.
[8]陈刚. 反应堆子通道内超临界水流动传热特性数值模拟研究[D]. 郑州:华北水利水电大学电力学院,2015.
[9]舒曦. 超临界水反应堆传热分析[J]. 科技视界,2018(5):51-52.
Shu Xi.Supercritical water reactor heat transfer analysis[J]. Science & Technology Vision,2018(5):51-52.
[10]王为术,崔强,陈刚,等. 反应堆子通道内超临界水传热特性数值研究[C]//全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会.北京:清华大学先进反应堆工程与安全教育部重点实验室,2015.
[11]Zhang L,Liu M,Dong Q,et al. Numerical research of heat transfer of supercritical CO2 in channels[J]. Energy and Power Engineering,2011,3(2):167-173.
[12]Zhao Houjian,Li Xiaowei,Wu Xinxin. Numerical investigation of supercritical water turbulent flow and heat transfer characteristics in vertical helical tubes[J]. Journal of Supercritical Fluids,2017,127:48-61.
[13]朱海雁,闫晓,曾小康,等. 带螺旋肋片方环管内超临界水流动传热特性数值研究[J]. 核动力工程,2013,34(2):34-40.
Zhu Haiyan,Yan Xiao,Zeng Xiaokang,et al. CFD analysis of effect of helix rib on flow and heat transfer of supercritical water in square annular channel[J]. Nuclear Power Engineering,2013,34(2):34-40.
[14]Pioro I,Mokry S. Thermophysical properties at critical and supercritical pressures[EB/OL]. http://www.doc88.com/p-6681598193042.html,2019-04-11.
[15]Glushchenko L,Gandziuk O. Temperature conditions at the wall of an annular channel with internal heating at supercritical pressures[J]. High Temperature,1973,10(4):734-738.
[16]Yamagata K,Yoshida S,Fujii T,et al. Forced convective heat-transfer to supercritical water flowing in tubes[J]. International Journal of Heat and Mass Transfer,1972,15(12):2575-2593.
[17]Zhu Y. Numerical investigation of the flow and heat transfer within the core cooling channel of a supercritical water reactor[D]. Stuttgart,Germany Universit?t Stuttgart,Institut für Kernenergetik,2010.
[18]Sharma D,Pandey K M. Computational study of effect of increasing heat flux on convective heat transfer in sub channels of carbon dioxide flow at pressure above critical value[J]. Applied Mechanics and Materials,2015,772:8-13.
[19]Kim H,Kim H Y,Song J H,et al. Heat transfer to supercritical pressure carbon dioxide flowing upward through tubes and a narrow annulus passage[J]. Progress in Nuclear Energy,2008,50(2/6):518-525.
[20]Dang C,Hihara E. In-tube cooling heat transfer of supercritical carbon dioxide. Part 1. Experimental measurement[J]. International Journal of Refrigeration,2004,27(7):736-747.
[21]郑岚,陈开勋. 超(近)临界水的研究和应用现状[J]. 石油化工,2012,41(6):621-629.
Zheng Lan,Chen Kaixun. Development and application of supercritical and near-critical H2O[J]. Petrochemical Technology,2012,41(6):621-629.
[22]Wagner W. International steam tables:Properties of water and steam based on the industrial formulation IAPWS-IF97[M]. Berlin,Germany:Springer-Verlag Berlin Heidelberg,2007.
[23]Ornatskii A,Glushchenko L,Kalachev S. Heat transfer with rising and falling flows of water in tubes of small diameter at supercritical pressures[J]. Thermal Engineering,1971,18(5):137-141.

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Last Update: 2019-06-30