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Volume 45 Issue 5
Oct.  2024
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Liu Luguo, Jiang Guangming, Xia Yunfeng, Liang Yu, Wang Mingjun, Liu Yu. Research on Multi-scale Coupling Simulation of Rod Bundle Channels Based on Subchannel-CFD Coupling Code[J]. Nuclear Power Engineering, 2024, 45(5): 256-261. doi: 10.13832/j.jnpe.2024.05.0256
Citation: Liu Luguo, Jiang Guangming, Xia Yunfeng, Liang Yu, Wang Mingjun, Liu Yu. Research on Multi-scale Coupling Simulation of Rod Bundle Channels Based on Subchannel-CFD Coupling Code[J]. Nuclear Power Engineering, 2024, 45(5): 256-261. doi: 10.13832/j.jnpe.2024.05.0256

Research on Multi-scale Coupling Simulation of Rod Bundle Channels Based on Subchannel-CFD Coupling Code

doi: 10.13832/j.jnpe.2024.05.0256
  • Received Date: 2023-10-31
  • Rev Recd Date: 2024-01-19
  • Publish Date: 2024-10-14
  • When the subchannel code is used for core thermal hydraulic analysis, it is necessary to give the real-time information such as the state parameters of the core inlet, and the computational fluid dynamics (CFD) code can calculate the fine thermal hydraulic parameters of the core inlet. In this paper, the subchannel code CORTH is explicitly coupled with the CFD code FLUENT by means of internal coupling method and dynamic link library technology. The coupling code is further used to simulate the experimental conditions of PNL 2×6 benchmark problem, in which FLUENT calculates the inlet section to provide accurate inlet flow distribution for CORTH, while CORTH calculates the simulated heating section. The results show that the multi-scale coupling code can realize the real-time transmission of thermal parameter information between sub-channel code and CFD code, and the simulation results are in good agreement with the experimental results.

     

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