Instability Analysis of Two-Phase Flow in Parallel Rectangular Channels for Compact Nuclear Reactors
In this paper, a numerical study of two-phase flow instability in parallel rectangular channels is presented. Using the homogeneous flow model, marginal stability boundaries (MSBs) are derived in the parameter space defined by the phase change number (Npch) and subcooling number (Nsub) under various operating conditions. Comparison with experimental data shows that the model predicts stability trends with a deviation of ±12.5%. The study reveals that, under constant mass flux conditions, stability decreases as the equivalent diameter (De) of the channels increases. Additionally, the exit area ratio of the two parallel tubes has minimal effect on the MSB, indicating that exit geometry does not significantly influence system stability. However, an increase in the inlet area ratio, from 0.1 to 1, reduces system stability, suggesting that larger inlet areas relative to tube cross-sectional areas may lead to greater flow disturbances, thereby decreasing stability. Moreover, increasing the length of the tubes enhances system stability, which may be attributed to the extended development length allowing for dissipation of flow disturbances. The study further demonstrates that higher flow rates, between 0.15 kg/s and 0.25 kg/s, enhance stability, while increasing the outlet flow resistance coefficient reduces stability. Conversely, increasing the inlet flow resistance coefficient improves stability. At system pressures of 3 MPa, 6 MPa, and 9 MPa, it is observed that higher pressures shift the boundary of complete vaporization (Xe = 1) to the left on the Npch and Nsub graph, reducing the region susceptible to instability. The study also employs Fast Fourier Transform (FFT) analysis to identify peak frequencies across different parameter ranges. By examining the stability map and frequency spectra, the study provides deeper insights into two-phase flow instabilities in parallel channels.
Authors
- Qiang Lian (ORCID: https://orcid.org/0000-0001-7892-114X)
- Wan Sun (ORCID: https://orcid.org/0000-0003-4484-5155)
- Meiyue Yan (ORCID: https://orcid.org/0009-0008-9224-3865)
- Can Wang (ORCID: https://orcid.org/0000-0003-1641-2395)
- Simiao Tang (ORCID: https://orcid.org/0000-0002-8918-172X)
- Liangming Pan
- Quan-yao Ren (ORCID: https://orcid.org/0000-0003-3195-618X)
- Longxiang Zhu
- Zaiyong Ma
- Luteng Zhang
- Calvin Febianto Liem
Institutions
- Chongqing University (CN)
- National University of Singapore (SG)
Publication Details
- Journal
- Energies
- Published
- 2025-04-16
- DOI
- https://doi.org/10.3390/en18082049
- Primary Topic
- Nuclear Engineering Thermal-Hydraulics
- Type
- article
- Field-Weighted Citation Impact
- 0.00
Funders
- National Natural Science Foundation of China
- Natural Science Foundation of Chongqing