Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model
Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model作者机构:School of Nuclear Science and TechnologyUniversity of Science and Technology of ChinaHefei 230026China
出 版 物:《Nuclear Science and Techniques》 (核技术(英文))
年 卷 期:2022年第33卷第3期
页 面:30-44页
核心收录:
学科分类:082703[工学-核技术及应用] 08[工学] 0827[工学-核科学与技术]
主 题:Subchannel method Code development Blockage accident Liquid-metal-cooled fast reactor
摘 要:To predict the thermal-hydraulic(T/H)parameters of the reactor core for liquid-metal-cooled fast reactors(LMFRs),especially under flow blockage accidents,we developed a subchannel code called KMC-FB.This code uses a time-dependent,four-equation,singlephase 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 crossflow,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 validation,we compared our results with the experimental data of the NACIE-UP BFPS blockage test and the KIT19ROD blockage test.The results revealed that KMC-FB has sufficient solution accuracy and can be used in future flow blockage analyses for LMFRs.