Numerical simulation in a subcooled water flow boiling for one-sided high heat flux in reactor divertor

•The Eulerian multiphase models coupled with Non-equilibrium Boiling model can effectively simulate the subcooled water flow boiling.•ONB and FDB appear earlier and earlier with the increase of heat fluxes.•The void fraction increases gradually along the flow direction.•The inner CuCrZr tube deterio...

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Bibliographic Details
Published in:Fusion engineering and design 2016-11, Vol.112, p.587-593
Main Authors: Liu, P., Peng, X.B., Song, Y.T., Fang, X.D., Huang, S.H., Mao, X.
Format: Article
Language:English
Subjects:
Boiling water reactors
Computer simulation
Copper
Enhancement of heat transfer
Fusion
Heat flux
Heat transfer
Heating
Mathematical models
Nucleate boiling
Numerical simulation
One-sided heating
Subcooled water flow boiling
Tungsten
Two phase flow
Void fraction
Water flow
Water-cooled W/Cu divertor
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Summary:•The Eulerian multiphase models coupled with Non-equilibrium Boiling model can effectively simulate the subcooled water flow boiling.•ONB and FDB appear earlier and earlier with the increase of heat fluxes.•The void fraction increases gradually along the flow direction.•The inner CuCrZr tube deteriorates earlier than the outer tungsten layer and the middle OFHC copper layer. In order to remove high heat fluxes for plasma facing components in International Thermonuclear Experimental Reactor (ITER) divertor, a numerical simulation of subcooled water flow boiling heat transfer in a vertically upward smooth tube was conducted in this paper on the condition of one-sided high heat fluxes. The Eulerian multiphase model coupled with Non-equilibrium Boiling model was adopted in numerical simulation of the subcooled boiling two-phase flow. The heat transfer regions, thermodynamic vapor quality (xth), void fraction and temperatures of three components on the condition of the different heat fluxes were analyzed. Numerical results indicate that the onset of nucleate boiling (ONB) and fully developed boiling (FDB) appear earlier and earlier with increasing heat flux. With the increase of heat fluxes, the inner CuCrZr tube will deteriorate earlier than the outer tungsten layer and the middle oxygen-free high-conductivity (OFHC) copper layer. These results provide a valuable reference for the thermal-hydraulic design of a water-cooled W/Cu divertor.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2016.05.010