ANALYSIS ON TWO PHASE FLOW BEHAVIOR FOR NATURALCIRCULATION SYSTEM IN 5MW NUCLEAR HEATING REACTOR
B Oujie
Abstract
B Oujie
Abstract
The experiment was carried out on a test loop HRTL 5 simulating the geometry and system design of the 5MW Nuclear heating reactor,while the analysis was based on a one dimensional two phase flow drift model with conservation equations for mass,steam,energy and momentum.Clausius Clapeyron equation was used for the calculation of flashing front in the riser.A set of ordinary differential equation,describing the behavior of two phase flow in the natural circulation system,was derived through integration of the above conservation equations in subcooled boiling region,bulk boiling region in the heated section and in the riser.The method of time domain was used for the calculation.The results show that,firstly,subcooled boiling in the heated section and void flashing in the riscr have signifiacnt influence on the distribution of the void fraction,mass flow rate and stability of the system,espccially at lower pressure;secondly,in a wide range of two phase flow conditions,only subcooled boiling occurs in the heated section.The propagation behavior of flow oscillation was also studied.Calculated results agree with experimental data well at the 5MW nuclear reactor conditions.
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The experiment was carried out on a test loop HRTL 5 simulating the geometry and system design of the 5MW Nuclear heating reactor,while the analysis was based on a one dimensional two phase flow drift model with conservation equations for mass,steam,energy and momentum.Clausius Clapeyron equation was used for the calculation of flashing front in the riser.A set of ordinary differential equation,describing the behavior of two phase flow in the natural circulation system,was derived through integration of the above conservation equations in subcooled boiling region,bulk boiling region in the heated section and in the riser.The method of time domain was used for the calculation.The results show that,firstly,subcooled boiling in the heated section and void flashing in the riscr have signifiacnt influence on the distribution of the void fraction,mass flow rate and stability of the system,espccially at lower pressure;secondly,in a wide range of two phase flow conditions,only subcooled boiling occurs in the heated section.The propagation behavior of flow oscillation was also studied.Calculated results agree with experimental data well at the 5MW nuclear reactor conditions.
Key concepts: Subcooling, Flashing, Natural circulation, Boiling, Mechanics, Thermodynamics, Two-phase flow, Nuclear reactor