Abstract
During the working period of decay heat removal system, the flow rate of liquid sodium in wire-wrapped fuel assembly is very low, generally Re < 1000 . In the present study, both experimental methods and numerical simulation methods are applied. First, water experiment of 37-pin wire-wrapped rod bundle was carried out. Then, the numerical simulation study was carried out, the experimental data and the numerical simulation results were compared and analyzed, and a suitable turbulence model was selected to simulate the liquid sodium medium. Finally, numerical simulations under different boundary conditions were performed. Results indicate that except for the low Reynolds number k - ε turbulence model, other turbulence models have little difference with the experimental results. The results of realizable k - ε turbulence model are the most close to the experimental results. Compared with the friction factor obtained by using water medium and liquid sodium medium, the calculation results of water medium and sodium medium under the same condition are basically consistent, with the deviation within 1%. The reason is that the velocity of water is higher than sodium medium at the same Reynolds number, and the transverse disturbance caused by helical wire is larger.
Highlights
Nuclear power, which has been around for decades, is one of the essential powers in energy fields
The passive safety technology is generally used in a sodium cooled fast reactor, which is introduced into the third-generation nuclear power plant
Gajapathy et al [2] make the analysis of the impact on the helical wires around a 217-pin fuel bundle at high Reynolds number equal to 95000 by computational fluid dynamics (CFD), the research of the resistance friction tending to be reduced as the helical pitch becoming increased, and the conclusion of the temperature gradient getting down with the transverse flowing in the assembly
Summary
Nuclear power, which has been around for decades, is one of the essential powers in energy fields. Gajapathy et al [2] make the analysis of the impact on the helical wires around a 217-pin fuel bundle at high Reynolds number equal to 95000 by computational fluid dynamics (CFD), the research of the resistance friction tending to be reduced as the helical pitch becoming increased, and the conclusion of the temperature gradient getting down with the transverse flowing in the assembly. Cheng and Todreas [10] presented a series of experiments on the 37pin rod bundle test section He used isokinetic sampling probes to measure the flow rate of the subchannels and evaluated the mixing by introducing a salt tracer into the bundle. Cheng et al [14] analyzed the hydraulic characteristics of different kinds of wire-wrapped rod bundle assemblies of China Experimental Fast Reactor (CEFR) under low Reynolds number by using CFX program. Liquid sodium flowing in wire-wrapped fuel assembly is considered low during the decay heat removal, generally Re < 1000. The overall study was made to illustrate the impact on resistance characteristics in the 37-rod fuel assembly under the heating
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