Flow and heat transfer evaluation of lead-bismuth eutectic coolant for nuclear power application

2021 ◽  
Vol 385 ◽  
pp. 111550
Author(s):  
Chen Wang ◽  
Chenglong Wang ◽  
Yan Zhang ◽  
Dalin Zhang ◽  
Wenxi Tian ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Nuclear Power ◽  
Flow And Heat Transfer ◽  
Lead Bismuth Eutectic ◽  
Power Application

Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions

2021 ◽  
Vol 382 ◽  
pp. 111373
Author(s):  
Zhipeng Liu ◽  
Daishun Huang ◽  
Chenglong Wang ◽  
Qifan Yu ◽  
Dalin Zhang ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Heat Transfer Analysis ◽  
Flow And Heat Transfer ◽  
Lead Bismuth Eutectic

Numerical Simulation of Fluid Flow and Heat Transfer Under Flow Fluctuation Condition in Horizontal Tube

2010 ◽  
Author(s):  
Yusheng Liu ◽  
Puzhen Gao ◽  
Dianchuan Xing
Keyword(s):  
Heat Transfer ◽  
Fluid Flow ◽  
Nuclear Power ◽  
Cfd Simulation ◽  
Horizontal Tube ◽  
Heat Fluxes ◽  
Practical Significance ◽  
Flow And Heat Transfer ◽  
Flow Fluctuation ◽  
Computational Fluid Dynamics Cfd

Fluctuating flow is widely presented in nuclear power plant operating procedure. When the fluctuating flow occurs in the loop, the fluid flow and heat transfer in the core will be affected, which makes the study of flow fluctuation have more practical significance. With computational fluid dynamics (CFD), characteristics of fluid flow and heat transfer are numerically simulated in a horizontal tube under periodical fluctuating flow. The influences of different factors on the fluid flow and heat transfer are analyzed. The simulation results of steady flow and heat transfer in horizontal tube agree with the traditional empirical correlations’ results, which validates the feasibility of doing this research using CFD simulation. The horizontal tube fluctuation flow and heat transfer with different flow fluctuation periods, fluctuation relative amplitudes and heat fluxes are numerically simulated. The results show that the smaller the flow fluctuation period is, the larger the flow fluctuation relative amplitude we get, and the more evident influence of flow fluctuation on fluid flow and heat transfer can be found. The larger the heat flux is, the larger amplitude of temperature fluctuation of fluid will be. What is more, there is a lag in phase between friction coefficient and velocity, which is not presented between heat transfer coefficient and velocity.

Evaluation of the Flow and Heat Transfer Characteristic in Vertical Narrow Annulus Channel Based on the RELAPSCDAPSIM/MOD3.4 Code

2009 ◽  
Author(s):  
Jiange Liu ◽  
Minjun Peng
Keyword(s):  
Heat Transfer ◽  
Heat Transfer Characteristic ◽  
Nuclear Power ◽  
Flow Instability ◽  
Physical Phenomenon ◽  
Transfer Characteristic ◽  
Fluid Temperature ◽  
Experiment Data ◽  
Flow And Heat Transfer ◽  
Temperature Heat

The physical phenomenon of the flow and heat transfer characteristic in vertical narrow annulus channel is a little different from general channel. It is valuable to improve the model veracity for exactly predicting the nuclear power system key physical phenomenon. The heat transfer characteristic of two narrow annulus channels (narrow gap 1.0mm and 1.5mm) is analyzed by means of the RELAPSCDAPSIM/MOD3.4 code recently developed by SDTP. Compared with related experiment data, the results show that the new developed code could predict key parameters such as fluid temperature, wall temperature, heat transfer coefficient, pressure drop, the occurrence condition of the flow instability and so on. The code has the ability to simulate the narrow annulus channel heat transfer characteristic.

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