As the conventional core analysis codes are designed for the land-based reactor core, a thermal-hydraulic subchannel analysis code for motion conditions (SACROM) is developed. To evaluate the effect of different motion conditions on coolant flow, the model of additional forces is established. To check the accuracy of the models, the code has been verified by test data, a commercial subchannel code and a CFD code. In the steady-state verification, the ISPRA data were used and the predicted results agree well with the test data. For the transient simulations without motion conditions, the code COBRA-EN was chosen and the results from SACROM fit the results from COBRA-EN well. And CFX code was used to verify the accuracy of the model of additional forces for motion conditions. The results show that the code can be used in the thermal hydraulic characteristics of the reactor core under motion conditions.
- Nuclear Engineering Division
Development and Verification of Thermal Hydraulic Subchannel Analysis Code for Motion Conditions
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Cai, R, Huang, S, Wang, K, Tian, W, Qiu, S, & Su, G. "Development and Verification of Thermal Hydraulic Subchannel Analysis Code for Motion Conditions." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T10A016. ASME. https://doi.org/10.1115/ICONE24-60394
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