Mechanical non-homogeneous and thermal non-equilibrium phenomenon exists in two-phase critical flow compared with single phase flow. A one-dimensional two-fluid critical flow model is developed for initially subcooled water flowing in pipe or orifices. The model accounts for thermal nonequilibrium between the liquid and vapor bubbles and for interphase relative motion. In this model, an improved correlation to calculate flashing inception location and surperheat is proposed. The model consists of six conservation equations as well as a seventh equation representing bubble growth in bubbly flow. Closure of the set of governing equations is performed with constitutive relationships which determine the interfacial momentum terms due to mass exchange, wall to liquid and wall to vapour frictional forces, liquid to gas interfacial force and interfacial heat transfer rate. The model considers the development of three flow regimes, namely, bubbly, churn and annular flow regimes. Model predictions compare favorably with experimental data over a wide range of pressures and pipe diameters and lengths.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5149-4
PROCEEDINGS PAPER
A Choking Model With Thermal Non-Equilibrium for Initially Subcooled Water
Lv Yufeng,
Lv Yufeng
China Institute of Atomic Energy, Beijing, China
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Zhao Minfu,
Zhao Minfu
China Institute of Atomic Energy, Beijing, China
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Li Weiqing
Li Weiqing
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Lv Yufeng
China Institute of Atomic Energy, Beijing, China
Zhao Minfu
China Institute of Atomic Energy, Beijing, China
Li Weiqing
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE26-82207, V06BT08A039; 7 pages
Published Online:
October 24, 2018
Citation
Yufeng, L, Minfu, Z, & Weiqing, L. "A Choking Model With Thermal Non-Equilibrium for Initially Subcooled Water." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6B: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06BT08A039. ASME. https://doi.org/10.1115/ICONE26-82207
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