Study on natural circulation flow stagnation and critical heat flux in narrow rectangular channel
- 1. Institute of Nuclear Thermal-Hydraulic Safety and Standardization, North China Electric Power University, Beijing (China)
- 2. CNNC Key Laboratory on Nuclear Power Thermal Hydraulic Technology, Nuclear Power Institute of China, Chengdu (China)
Description
Experiments of critical heat flux (CHF) under natural circulation condition in narrow rectangular channel were conducted in Natural Circulation Laboratory of North China Electric Power University. The phenomena of flow stagnation and heat transfer deterioration were observed during the experiments. The developing mechanism of flow stagnation/heat transfer deterioration in narrow rectangular channel under saturation condition was proposed. Flow pattern instability would appear when the flow excursion occurred, thus leading to the continuous flow oscillation and flow stagnation. Then the liquid layer near the outlet would completely evaporate under a certain heat condition, and the CHF occurred. While in narrow rectangular channel, the vapor stream could produce extrusion action to the liquid layer on the heating wall due to the limitation caused by gap size, which cause the liquid to become very thin and heat transfer deterioration could happen under a much lower heat flux condition. Based on the mechanistic analysis, a corresponding calculation model was provided. A dimensionless number of constraints and a natural circulation characteristic factor were brought in to optimize the proposed model for the purpose of considering the effects of gap size and circulation mode in the model respectively. The multiple regressions were applied to the calculation model according to the experimental results, and the accuracy of which was validated. The comparison between experimental results and model calculation values indicated that CHF would increase with the inlet velocity and system pressure increased, and would decrease with the outlet quality increased. (authors)
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 33
- Journal Issue
- 1
- Journal Page Range
- p. 65-75
- ISSN
- 0258-0918
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 46127572
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- CHINA; COMPARATIVE EVALUATIONS; CRITICAL HEAT FLUX; DATA; EDUCATIONAL FACILITIES; EXCURSIONS; FLUID FLOW; INSTABILITY; LAYERS; LIMITING VALUES; NATURAL CONVECTION; OSCILLATIONS; RECTANGULAR CONFIGURATION; SATURATION; STAGNATION; VAPORS
- Descriptors DEC
- ACCIDENTS; ASIA; CONFIGURATION; CONVECTION; ENERGY TRANSFER; EVALUATION; FLUIDS; GASES; HEAT FLUX; HEAT TRANSFER; INFORMATION; MASS TRANSFER; REACTOR ACCIDENTS
Optional Information
- Notes
- 9 figs., 17 refs. FDS Team