Theoretical Investigation on Thermal Hydraulic Characteristics of Boiling Two-Phase Sodium

Qiu Zicheng; Lan Zhike; Ma Zaiyong; Qiu Suizheng; Zan Yuanfeng; Xing Dianchuan; Li Yongliang

doi:10.13832/j.jnpe.2016.S2.0121

Volume 37 Issue S2

Feb. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2016 > 37(S2): 121-124

Qiu Zicheng, Lan Zhike, Ma Zaiyong, Qiu Suizheng, Zan Yuanfeng, Xing Dianchuan, Li Yongliang. Theoretical Investigation on Thermal Hydraulic Characteristics of Boiling Two-Phase Sodium[J]. Nuclear Power Engineering, 2016, 37(S2): 121-124. doi: 10.13832/j.jnpe.2016.S2.0121

Citation:

Qiu Zicheng, Lan Zhike, Ma Zaiyong, Qiu Suizheng, Zan Yuanfeng, Xing Dianchuan, Li Yongliang. Theoretical Investigation on Thermal Hydraulic Characteristics of Boiling Two-Phase Sodium[J]. Nuclear Power Engineering, 2016, 37(S2): 121-124. doi: 10.13832/j.jnpe.2016.S2.0121

Citation:

Qiu Zicheng, Lan Zhike, Ma Zaiyong, Qiu Suizheng, Zan Yuanfeng, Xing Dianchuan, Li Yongliang. Theoretical Investigation on Thermal Hydraulic Characteristics of Boiling Two-Phase Sodium[J]. Nuclear Power Engineering, 2016, 37(S2): 121-124. doi: 10.13832/j.jnpe.2016.S2.0121

PDF( 336 KB)

Theoretical Investigation on Thermal Hydraulic Characteristics of Boiling Two-Phase Sodium

doi: 10.13832/j.jnpe.2016.S2.0121

1. CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610213, China;
2. Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China

Received Date: 2016-10-09
Rev Recd Date: 2016-12-20

Available Online: 2025-02-15

Publish Date: 2025-02-15

Abstract

Abstract

Based on the experimental work, thermal hydraulic characteristics of sodium boiling are theoretically researched. The object of calculation is an annulus. Liquid sodium is considered incompressible while sodium vapor is considered compressible. Homogeneous flow model is used in the two phase region and upwind scheme integral is used during the calculation. The calculated results showed good agreement with the experimental data, moreover, this work shows good predictive ability as expansion of the experiments.
- Liquid sodium,
- Annuli,
- Boiling

FullText(HTML)

References(0)

References

Relative Articles

[1]	Liu Hao, Zhang Luteng, Zhou Wenxiong, Zhu Longxiang, Wan Lingfeng, Zhang Hong, Ma Zaiyong, Sun Wan, Pan Liangming, Deng Jiewen. Experimental Investigation on Void Fraction Distribution of Boiling Flow in 2×2 Rod Bundle Channel[J]. Nuclear Power Engineering, 2023, 44(6): 104-110. doi: 10.13832/j.jnpe.2023.06.0104
[2]	Cao Chengque, Kuang Bo, Zhao Yu, Deng Jian, Ding Shuhua, Wu Dan. Experimental Study on Onset of Boiling in Rectangular Narrow Channel with Large Aspect Ratio[J]. Nuclear Power Engineering, 2023, 44(1): 24-31. doi: 10.13832/j.jnpe.2023.01.0024
[3]	Liang Yu, Wang Xiaoyu, Deng Jian, Liu Yu, Song Gongle, Zhong Ruicheng, Zhang Dalin, Zhu Dahuan. Research on Simulation Approach of Inter-wrapper Flow in Liquid Metal Cooled Fast Reactor Based on Subchannel Method[J]. Nuclear Power Engineering, 2023, 44(S2): 61-66. doi: 10.13832/j.jnpe.2023.S2.0061
[4]	Zhu Longxiang, Zhang Luteng, Sun Wan, Ma Zaiyong, Pan Liangming. Identification of Flow Regime of Boiling Flow in a Vertical Annulus with Unsupervised Machine Learning[J]. Nuclear Power Engineering, 2023, 44(3): 112-120. doi: 10.13832/j.jnpe.2023.03.0112
[5]	Liu Haidong, Chen Deqi, Qin Jiang, Liu Hanzhou, Yan Peigang, Liu Wei. Visual Experimental Study on Boiling Crisis Induced by Flow Oscillation in a Single Rod Channel[J]. Nuclear Power Engineering, 2022, 43(1): 35-41. doi: 10.13832/j.jnpe.2022.01.0035
[6]	Ren Bing, Gan Fujun, Yang Ping. CFD Calculation and Analysis of Boiling Heat Transfer of Full-length Fuel Bundle with Bent Rod[J]. Nuclear Power Engineering, 2022, 43(6): 43-50. doi: 10.13832/j.jnpe.2022.06.0043
[7]	Yan Tianyu, Wang Teng, Bi Qincheng, Wang Zehao. Experimental Study on Heat Transfer Characteristics of Subcooled Flow Boiling in a Narrow Vertical Rectangular Channel[J]. Nuclear Power Engineering, 2021, 42(1): 35-41. doi: 10.13832/j.jnpe.2021.01.0035
[8]	He Xueqiang, Liu Hanzhou, Chen Deqi, Lu Qi. Automatic Image Recognition and Analysis of Bubble Behavior in Rectangular Narrow Channel[J]. Nuclear Power Engineering, 2020, 41(2): 6-10.
[9]	Numerical Simulation on Flow and Heat Transfer Characteristics of Sodium in an Annuli[J]. Nuclear Power Engineering, 2019, 40(3): 21-25. doi: 10.13832/j.jnpe.2019.03.0021
[10]	Dong Xiaomeng, Zhang Zhijian, Liu Dong, Tian Zhaofei, Chen Guangliang. Numerical Study on Boiling Critical Characteristics of Rod Beam Channel Positioning Lattice[J]. Nuclear Power Engineering, 2018, 39(6): 5-10. doi: 10.13832/j.jnpe.2018.06.0005
[11]	Wang Jinyu, Wang Jun, Zan Yuanfeng, Huang Jun. Experimental Study on Velocity of Quench Front during Reflooding Process in a Vertical Annual Channel[J]. Nuclear Power Engineering, 2018, 39(4): 63-66. doi: 10.13832/j.jnpe.2018.04.0063
[12]	Wang Jinyu, Wang Jun, Zan Yuanfeng, Huang Yanping. Experimental Study on Flow and Heat Transfer during Reflooding Process in a Vertical Annual Channel[J]. Nuclear Power Engineering, 2018, 39(4): 22-27. doi: 10.13832/j.jnpe.2018.04.0022
[13]	Hong Gang, Xu Zhigang, Bian Boshen, Zhang Yaoli, Yan Xiao, Huang Yanping. Predictive Study of Bubble Mean Diameter in Subcooled Flow Boiling[J]. Nuclear Power Engineering, 2017, 38(2): 184-188. doi: 10.13832/j.jnpe.2017.02.0184
[14]	Chen Chong, Meng Qingzheng, Wu Wei, Liu Dongmin, Gao Puzhen. Prediction Model of Boiling Heat Transfer Coefficient in Rectangular Narrow Channel[J]. Nuclear Power Engineering, 2017, 38(2): 175-178. doi: 10.13832/j.jnpe.2017.02.0175
[15]	Lu Qi, Chen Deqi, Song Jiaban, Pan Ruian, Tang Tao, Pan Liangming. Experimental Research on FCI Process of High Superheated Molten Metals[J]. Nuclear Power Engineering, 2016, 37(3): 158-162. doi: 10.13832/j.jnpe.2016.03.0158
[16]	Luo Feng. Experimental Investigation on Heat Transfer Characteristic of Saturated Boiling in Round Tube[J]. Nuclear Power Engineering, 2015, 36(S1): 184-186. doi: 10.13832/j.jnpe.2015.S1.0184
[17]	ZHAO Shufeng, JIANG Hua. Improvement of Sodium Boiling Model in Accident Simulation[J]. Nuclear Power Engineering, 2014, 35(2): 21-26.
[18]	ZHANG Xiao-ning, SUN Zhong-ning, MENG Xian-ke, XU Guang-zhan. Experimental Investigation of Subcooled Flow Boiling Incipience in Volumetrically Heated Packed Bed[J]. Nuclear Power Engineering, 2013, 34(3): 58-62.
[19]	WANG Mei, WU Ying-wei, TIAN Wen-xi, SU Guang-hui, QIU Sui-zheng. Turbulent Heat Transfer Characteristics of Liquid Sodium Flow in An Annular Tube[J]. Nuclear Power Engineering, 2013, 34(4): 53-57.
[20]	LI Hongbo, CHEN Bingde, XIONG Wanyu. Experimental Study on Post-Dryout Transition Boiling Heat Transfer in Rectangular Channel[J]. Nuclear Power Engineering, 2011, 32(4): 52-57.