Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model

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

doi:10.1007/s41365-022-01010-4

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Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2022-05-17

- 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
- Nuclear Science and Techniques 2022年33卷第3期文章编号：27
- Affiliations：
  
  1.School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China
- Author bio：
  
  hlchen1@ustc.edu.cn
- Funds：
- DOI：10.1007/s41365-022-01010-4
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Xiao Luo, Lian-Kai Cao, Wen-Pei Feng, 等. Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model[J]. Nuclear Science and Techniques, 2022,33(3):27

Xiao Luo, Lian-Kai Cao, Wen-Pei Feng, et al. Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model[J]. Nuclear Science and Techniques, 2022,33(3):27
Xiao Luo, Lian-Kai Cao, Wen-Pei Feng, 等. Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model[J]. Nuclear Science and Techniques, 2022,33(3):27 DOI： 10.1007/s41365-022-01010-4.

Xiao Luo, Lian-Kai Cao, Wen-Pei Feng, et al. Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model[J]. Nuclear Science and Techniques, 2022,33(3):27 DOI： 10.1007/s41365-022-01010-4.

摘要

Abstract

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, 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 validation, 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.

关键词

Keywords

Subchannel methodCode developmentBlockage accidentLiquid metal cooled fast reactor

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