To predict the thermal-hydraulic(T/H)param-eters of the reactor core for liquid-metal-cooled fast reactors(LMFRs),especially under flow blockage acci-dents,we developed a subchannel code called KMC-FB.This code uses a time-dependent,four-equation,single-phase flow model together with a 3D heat conduction model for the fuel rods,which is solved by numerical methods based on the finite difference method with a staggered mesh.Owing to the local effect of the blockage on the flow field,low axial flow,increased forced cross-flow,and backflow occur.To more accurately simulate this problem,we implemented a robust and novel solution method.We verified the code with a low-flow(～0.01 m/s)and large-scale blockage case.For the preliminary val-idation,we compared our results with the experimental data of the NACIE-UP BFPS blockage test and the KIT 19ROD blockage test.The results revealed that KMC-FB has sufficient solution accuracy and can be used in future flow blockage analyses for LMFRs.

Xiao Luo;Lian-Kai Cao;Wen-Pei Feng;Hong-Li Chen

School of Nuclear Science and Technology,University of Science and Technology of China,Hefei 230026,China

核技术（英文版）

[1]Xiao Luo;Lian-Kai Cao;Wen-Pei Feng;Hong-Li Chen-.Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model)[J].核技术（英文版）,2022(03):30-44

subchannel,LMFRs,NACIE,BFPS,19ROD

Development,code,blockage,accidents,fuel,model,To,predict,thermal,hydraulic,param,eters,core,liquid,metal,cooled,fast,reactors,especially,under,we,developed,called,KMC,FB,This,uses,dependent,four,equation,single,phase,together,heat,conduction,rods,which,solved,by,numerical,methods,finite,difference,staggered,mesh,Owing,local,effect,field,axial,increased,forced,cross,backflow,occur,more,accurately,simulate,this,problem,implemented,robust,novel,solution,We,verified,large,scale,case,For,preliminary,val,idation,compared,results,experimental,data,UP,test,KIT,revealed,that,sufficient,accuracy,can,be,used,future,analyses

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