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Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions.
- Source :
-
Nuclear Engineering & Design . Oct2021, Vol. 382, pN.PAG-N.PAG. 1p. - Publication Year :
- 2021
-
Abstract
- • The thermal–hydraulic characteristics of lead–bismuth eutectic in a vertical tube under rolling conditions are numerically investigated. • It is concluded that the frictional resistance coefficient and heat transfer correlations now used are not suitable for the ship-based LFR. • Comparison with water coolant shows that the enhancement of radial secondary flow is the main cause for the change of heat transfer ability of coolant. The investigation of flow and heat transfer of lead–bismuth eutectic (LBE) under rolling conditions is vital to the application of LBE cooled reactor in offshore engineering. In this paper, mature numerical method for modelling low Prandtl number liquid metal is used for LBE flow in a vertical tube under rolling conditions. Reynolds stress turbulent model is chosen to consider the complex secondary flow caused by additional force. It is found that the transverse additional force is the main reason accounting for the enhancement of heat transfer and secondary flow. The transient maximum heat transfer ability can be enlarged by 18% under condition of rolling angle of 30° and period of 8 s. And 10 times transverse additional force caused by rolling angle of 30° and period of 8 s is enough to change the flow resistance characteristic of LBE. Comparisons with water coolant indicate that the intensity of radial secondary flow play an important role in determining the heat transfer characteristic of fluid under rolling conditions. The high density and low Prandtl number also make the features of LBE under rolling conditions different from those of water. The empirical correlations used in system code now could not predict the flow and heat transfer of LBE under rolling conditions. Special attention should be paid to safety design criteria of the off-shore LBE cooled reactor. This paper may contribute to the thermal–hydraulic design of off-shore liquid metal cooled reactors. [ABSTRACT FROM AUTHOR]
Details
- Language :
- English
- ISSN :
- 00295493
- Volume :
- 382
- Database :
- Academic Search Index
- Journal :
- Nuclear Engineering & Design
- Publication Type :
- Academic Journal
- Accession number :
- 152496005
- Full Text :
- https://doi.org/10.1016/j.nucengdes.2021.111373