scholarly journals Heat transfer in coiled type superheater of moisture separator-reheater of turbines at the nuclear power plant

2019 ◽  
Vol 288 ◽  
pp. 012080 ◽  
Author(s):  
Mikle Egorov ◽  
A.A. Kalyutik ◽  
I. G. Akhmetova ◽  
S.O. Makoev
Keyword(s):  
Heat Transfer ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Moisture Separator

The Simulation Research of Noncondensable Gas to Condensation in Secondary Side Condenser of Floating Nuclear Power Plant Based on RELAP5

2018 ◽  
Author(s):  
Si-wei Yan ◽  
Chun-mei Li ◽  
Tie-bo Liang ◽  
Jing Zhao ◽  
Cheng-ming Hao ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Cooling Water ◽  
Gas Content ◽  
Simulation Research ◽  
Cooling Water Temperature ◽  
Noncondensable Gas ◽  
Secondary Side

Similar to conventional nuclear power plant, condensate water subcooling is a common problem in secondary coolant of floating nuclear power plant, which is caused by many reasons. In this article, RELAP5 is used to simulate the phenomenon of condensate water subcooling caused by noncondensable gas. The influence of noncondensable gas to condenser pressure, subcooling temperature, heat transfer rate, terminal temperature difference, cooling water temperature rise is presented. The results obtained through this study have shown that the model with non-condensable gas in steam can simulate condensate water subcooling, and reveal the discipline of condenser heat transfer characteristics as a function of noncondensable gas content.

Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT

2018 ◽  
Author(s):  
Xiaohan Zhao ◽  
Mingjun Wang ◽  
Wenxi Tian ◽  
G. H. Su ◽  
Suizheng Qiu
Keyword(s):  
Heat Transfer ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Pressure Drop ◽  
Nuclear Power ◽  
Reactor System ◽  
Economic Losses ◽  
Maximum Pressure ◽  
Hydraulic Characteristics ◽  
Tube Plugging

Steam Generator (SG) is a critical equipment in the nuclear power plant, it is the huge heat exchanger in reactor system which can achieve removing fission energy from the reactor system effectively to ensure safety of the whole nuclear system. It is located between the primary and the secondary loop in reactor system act as the intermediate hub of energy and the security barrier in nuclear power plant. Generally, there are numerous of U-shaped heat transfer tubes in SG it is one of the weakest structures throughout the primary loop system. So the integrity of the SG especially its heat transfer tubes is important to the safety of reactor operation. The degradation problem of heat transfer tubes together with ruptures accidents often occur under suffer environments in reactors, which include thermal stress, mechanical stress and so on, it is noteworthy that this kind of accidents is inevitable due to the limited properties of existing materials. The performance of the SG is seriously affected by the number of failure tubes. Plugging operations through various mechanical means is the most common method to solve the tubes ruptures problems which can reduce the economic losses to the utmost extent. However, plugging operations will make huge impact on the thermal hydraulic performances of both sides of SG. It’s meaningful to research the characteristics of the plugging affects under different operations. In this paper the hydraulic characteristics of primary side in AP1000 SG under a certain fraction of heat transfer tube plugging conditions is researched. Three dimensional hydraulic characteristics of primary side coolant in SG under different plugging conditions are obtained by using the thermal hydraulic software FLUENT. The typical plugging fraction in this simulation model is 10 percent, and the effect of plugging locations also be considered through changing the plugging positions using the zone marking method. The results shows that the pressure drop under the structure integrated SG is 358.01MPa which is accordance with the results from Westinghouse 343KPa. The pressure drop values varies when changing positions of the plugging tubes under the same plugging fraction condition. The flow fields in bottom head also change meanwhile and the maximum pressure drop can reach up to 388.05KPa when the plugging fraction is 10%. The growth rate become significant when tube plugging fraction larger than 5%, and differences between maximum and minimum values of total pressure drop under different plugging positions become larger gradually. Finally the local resistance coefficients and flow field distributions of primary side in SG under various plugging conditions are obtained which is meaningful for the reactor safety and it can be a good reference for the maintenance of SG.

Research of Seawater Effects on Thermal-Hydraulic Behavior at Severe Accident: 1 — Research Plan and Results of Preliminary Experiments

2013 ◽  
Author(s):  
Wei Liu ◽  
Taku Nagatake ◽  
Kazuyuki Takase ◽  
Hiroyuki Yoshida ◽  
Fumihisa Nagase
Keyword(s):  
Heat Transfer ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Salt Precipitation ◽  
Nuclear Power Plant Accident ◽  
Hydraulic Behavior ◽  
Current State ◽  
Research Plan ◽  
Fukushima Daiichi

The development of analytical method to predict and assess the current state of the reactor cores of Fukushima Daiichi nuclear power plant is required. Experimental researches are also required to obtain data to verify the analytical results and to understand the phenomena that are important to the accident progress evaluation. In the Fukushima Daiichi nuclear power plant accident, seawater was injected into the reactors to cool down nuclear fuels. Core cooling with seawater has never been assumed and the effect of seawater on heat transfer in core is not clear. Then, effects of seawater on thermal-hydraulic behavior must be investigated to understand the phenomena occurred in the accident and to evaluate current state of the reactor cores. In this series of research work, the effects of seawater on thermal-hydraulic behavior before and after degradation of the cores will be researched experimentally. Experimental results will be incorporated to numerical simulation codes to evaluate effects of seawater on the Fukushima Daiichi nuclear power plant accident. In the experimental research part, we have a plan performing two heat transfer experiments to evaluate thermal hydraulic performance of sea water and effects of salt precipitation. A precipitation state confirmation experiment is performed to obtain basic information required for the experiments with salt precipitation. In this paper, outline of the research plan is explained and the results of the precipitation state confirmation experiment is shown.

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