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- 검색키워드
- 저자 : Shen Geyu (검색결과 4 건)
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Liquid entrainment through a large-scale inclined branch pipe on a horizontal main pipe
Gu, Ningxin,Shen, Geyu,Lu, Zhiyuan,Yang, Yuenan,Meng, Zhaoming,Ding, Ming Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.6
T-junction structures play an important role in nuclear power plant systems. Research on liquid entrainment is mostly based on small-scale branch pipes (d/D ≤ 0.2) and attention paid to large-scale branch pipes (0.33 < d/D < 1) is insufficient. Accordingly, this study implements a series of experiments on the liquid entrainment of T-junction with different angles (32.2°,47.9°,62.3°,90°) through a large-scale branch (d/D = 0.675). The onset liquid entrainment is related to the gas phase Froude number Fr<sub>g</sub>, the dimensionless gas chamber height h<sub>b</sub>/d and the branch pipe angle 𝜃. As Fr<sub>g</sub> increases, h<sub>b</sub>/d also rises. With a constant h<sub>b</sub>/d, the onset liquid entrainment changes from droplets entrainment by the gas phase to that by the rising liquid film. The steady-state liquid entrainment is related to w<sub>3g</sub>, h/d and 𝜃. With constant w<sub>3g</sub> and h/d, the branch quality grows as the branch angle increases. With a certain h/d, the branch quality increases, as the w<sub>3g</sub> number increases.
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Liu, Ping,Shen, Geyu,Li, Xiaoyu,Gao, Jinchen,Meng, Zhaoming Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.3
The T-junction exists widely in industrial engineering, especially in nuclear power plants, which plays an important part in nuclear power reactor thermal-hydraulics. However, the existing prediction models of the liquid entrainment are mainly based on the small branches or small breaks while there are a few researches for large branches (d/D > 0.2). Referring to the classical models about the onset of liquid entrainment of the T-junction, most of previous models regard liquid as ideal working fluid and ignore surface tension. This paper aims to study the effect of surface tension on the liquid entrainment, and develops an improved model based on the reasonable assumption. The establishment of new model employs the methods of force analysis, dimensional analysis. Besides, the dimensionless Weber number is adopted innovatively into the model to show the effect of surface tension. What is more, in order to validate the new model, three kinds of working fluids with different surface tensions are creatively adopted in the experiments: water, silicone oil and ethyl alcohol. The final results show that surface tension has a nonnegligible effect on the onset of liquid entrainment in large branch T-junction. The new model is well matched with the experimental data.
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Development of analysis program for direct containment heating
Jiang Herui,Shen Geyu,Meng Zhaoming,Li Wenzhe,Yan Ruihao 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.8
Direct containment heating (DCH) is one of the potential factors leading to early containment failure. DCH is closely related to safety analysis and containment performance evaluation of nuclear power plants. In this study, a DCH prediction program was developed to analyze the DCH loads of containment vessel. The phenomenological model of debris dispersal, metal oxidation reaction, debris-atmospheric heat transfer and hydrogen jet burn was established. Code assessment was performed by comparing with several separate effect tests and integral effect tests. The comparison between the predicted results and experimental data shows that the program can predict the key parameters such as peak pressure, temperature, and hydrogen production in containment well, and for most comparisons the relative errors can be maintained within 20%. Among them, the prediction uncertainty of hydrogen production is slightly larger. The analysis shows that the main sources of the error are the difference of time scale and the oxidation of cavity debris
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Experimental study on the condensation of sonic steam in the underwater environment
Zhaoming Meng,Wei Zhang,Jiazhi Liu,Ruihao Yan,Geyu Shen 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.4
Steam jet condensation is of great importance to pressure suppression containment and automaticdepressurization system in nuclear power plant. In this paper, the condensation processes of sonic steamjet in a quiescent subcooled pool are recorded and analyzed, more precise understanding are got in directcontact condensation. Experiments are conducted at atmospheric pressure, and the steam is injected intothe subcooled water pool through a vertical nozzle with the inner diameter of 10 mm, water temperaturein the range of 25e60 C and mass velocity in the range of 320e1080 kg/m2s. Richardson number iscalculated based on the conservation of momentum for single water jet and its values are in the range of0.16e2.67. There is no thermal stratification observed in the water pool. Four condensation regimes areobserved, including condensation oscillation, contraction, expansion-contraction and double expansioncontractionshapes. A condensation regime map is present based on steam mass velocity and watertemperature. The dimensionless steam plume length increase with the increase of steam mass velocityand water temperature, and its values are in the range of 1.4e9.0. Condensation heat transfer coefficientdecreases with the increase of steam mass velocity and water temperature, and its values are in the rangeof 1.44e3.65 MW/m2 C. New more accurate semi-empirical correlations for prediction of the dimensionlesssteam plume length and condensation heat transfer coefficient are proposed respectively. Thediscrepancy of predicted plume length is within ± 10% for present experimental results and ± 25% forprevious researchers. The discrepancy of predicted condensation heat transfer coefficient is with ± 12%.
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