Numerical Analysis Of Flow And Heat Transfer In The Natural Cycle Experiment Section Of A Sodium Cold Fast Reactor(SFR)

Nuclear energy occupy an important position in the energy sector,Sodium cooled fast reactor(Sodium cooled fast reactors,SFRs)as six kind of fourth generation nuclear reactor in the most mature technology,basic can satisfy the requirement of commercial application of Dui Xing,possesses the advantages of value-added nuclear fuel and nuclear waste transmutation.In order to ensure the safety of nuclear reactor core in case of emergency,sodium cooled fast reactor is usually designed with passive waste heat emission system.During the discharge of waste heat from the accident,a complex natural circulation loop will be formed inside the core.It is of great significance to analyze the discharge of waste heat from the core to determine the artesian circulation flow distribution in the process.The sodium-cooled fast reactor multi-box component test bench is the type and number of simulation components currently included,which is the largest of the known experiments on the natural circulation sodium loop of the core and the most complete simulation of the natural circulation loop of the sodium-cooled fast reactor.Lively and as a result of the liquid sodium metal visibility,and the complexity of the experimental section of the internal structure,box in complete the three boxes on the experimental section,although you can according to the fluid mechanics analysis of heat transfer and flow in a qualitative analysis of components,but the details of the flow and heat transfer of the internal and the rationality of the distribution of internal monitoring,it is difficult to verify.In this paper,the commercial CFD simulation software Fluent was used to simulate the flow between boxes and the influence of heat transfer between boxes on the flow inside the box.After get flow calculation results between box,first by measuring temperature distribution are compared with the experiment,verify the applicability of the numerical simulation method,and the velocity analysis results can be used to explain the experimental structure zones within the period of the cause of the temperature distribution in the flat,also according to the distribution of velocity field to determine the fuel in the experimental area,the structure area and two interface flow process,and validate the feasibility experiment period of implementation of the three boxes.Through the numerical calculation of and internal flows,it is found that the temperature gradient change of the flow in the box is mainly affected by the heat transfer between boxes,and it is found that under the condition of low Reynolds number,the floating lift generated by the internal temperature difference caused by heat transfer will cause the change of the flow distribution inside the fuel assembly,thus resulting in the increase of the non-flow resistance inside the fuel assembly.