scholarly journals Reactor coolant pump shaft seal stability during station blackout

1987 ◽  
Author(s):  
D B Rhodes ◽  
R C Hill ◽  
R G Wensel
Keyword(s):  
Shaft Seal ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Pump Shaft ◽  
Station Blackout

Numerical Simulation of Interior Flow Field of Reactor Coolant Pump under Station Blackout Accident

2012 ◽  
Vol 455-456 ◽  
pp. 1002-1008 ◽  
Author(s):  
Yi Ming Xu ◽  
Shi Ming Xu
Keyword(s):  
Numerical Simulation ◽  
Flow Field ◽  
Internal Flow ◽  
Simulation Method ◽  
Governing Equations ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Internal Characteristic ◽  
Station Blackout ◽  
Interior Flow

Numerical simulation is used for researching the transient characteristic and internal characteristic of the reactor coolant pump under station blackout accident. The simulation method has been presented by analyzing difference scheme for governing equations. The analytical model of reactor coolant pump flow field has been established by analyzing adequately the influence of varying rotation speed to the pump external characteristic. Finally, the pump internal flow characteristic is exposed.

scholarly journals Main-coolant-pump shaft-seal reliability investigation. Interim report

1982 ◽  
Author(s):  
C.E. Fair ◽  
J.A. Marsi ◽  
A.O. Greer
Keyword(s):  
Interim Report ◽  
Shaft Seal ◽  
Coolant Pump ◽  
Pump Shaft

scholarly journals Decontamination of a Contaminated RCP Shaft Using the SP-HyBRID Process

Processes ◽  
2021 ◽  
Vol 9 (10) ◽  
pp. 1725
Author(s):  
Hee-Chul Eun ◽  
Na-On Chang ◽  
Wang-Kyu Choi ◽  
Sang-Yoon Park ◽  
Seon-Byeong Kim ◽  
...  
Keyword(s):  
Decontamination Factor ◽  
Hybrid Process ◽  
Waste Generation ◽  
Nuclear Facility ◽  
Experimental Conditions ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Pump Shaft ◽  
Shaft Surface ◽  
Coolant System

It is very important to minimize the waste generation for decontamination of the reactor coolant system in a nuclear facility. As an alternative to commercial decontamination technologies, an inorganic acid chemical decontamination (SP-HyBRID) process can be effectively applied to the decontamination because it can significantly reduce the waste generation. In this study, the decontamination of a contaminated reactor coolant pump shaft from a nuclear facility was conducted using the SP-HyBRID process. First, equipment for a mock-up test of the decontamination was prepared. Detailed experimental conditions for the decontamination were determined through the mock-up test. Under the detailed conditions, the contaminated shaft was successfully decontaminated. The dose rate on the shaft surface was greatly reduced from 1400 to 0.9 μSv/h, and the decontamination factor showed a very high value (>1500).

Flow Field Analysis of the Reactor Coolant Pump Internal Cooling Circulation

2017 ◽  
Author(s):  
Jie Qin ◽  
Qingmu Xu ◽  
Junkai Yuan ◽  
Kun Cai
Keyword(s):  
Heat Transfer ◽  
Flow Field ◽  
Three Dimensional ◽  
Flow Characteristics ◽  
Flow Distribution ◽  
Internal Cooling ◽  
Shaft Seal ◽  
Flow Area ◽  
Coolant Pump ◽  
Reactor Coolant

Reactor coolant pump (RCP) is one of the most critical devices in third generation of pressurized water reactor nuclear power plant. EMD shield pump and KSB wet winding pump are two representative kinds of RCPs without complex shaft seal system. Due to cancellation of shaft seal system, the entire rotors (including the flywheel) are immersed in the coolant. The losses in RCPs take one third of the total power including rotation loss caused by rotor in the water, electromagnetic loss in the shielding sleeve,the heat transferred through high temperature coolant, and heat generated by bearing.Because of the losses listed above, bearing and winding are heated,and the losses make temperature rise. in order to ensure that the motor is working properly at low temperatures, the company EMD and KSB design the RCP internal cooling circulation which brings the heat out to ensure the normal operation of the RCPs. The RCP internal cooling circulation includes inlet flow area, auxiliary impeller, thrust bearing, the lower flywheel, motor can, upper radial bearing, upper flywheel, outlet flow area, and external heat exchanger,etc. Flow characteristics in every flow path determine the flow distribution and heat transfer, and the flow distribution determines whether the cooling performance of RCP internal cooling circulation meets the requirements. In order to control operating temperature of motor and bearing, and to optimize heat transfer, adjusting the size of flow area and changing the flow characteristics arecritical. flow field and temperature field in RCP internal cooling circulation need overall analysis. Flow distribution can be obtained theoretically through the calculation of an overall three-dimensional model.But on the one hand, the calculation time is long due to a complex three-dimensional model with a large quantity of grids, on the other hand, it is easier to casue errors in local processing and the errors are difficult to find or correct. For rapid analysis and optimization of flow and heat transfer in RCP internal cooling circulation, ensure the motor winding and bearing operate at an appropriate temperature, the local characteristics of RCP internal cooling circulation are studied, one-dimensionalanalysis method of RCP internal cooling circulation is developed. This one-dimensional analysis method can be used to predict the flow distribution of each part of RCP internal cooling circulation according to change of the channel geometry parameters, key dimensions, boundary conditions and rotor speed. The geometric parameters are optimized by analyzing the flow distribution, and the purpose of design guidance are achieved.

Structural Integrity Assessment of the Pump Shaft Assembly of the APR1400 Reactor Coolant Pump

2010 ◽  
Author(s):  
Min-Chul Kim ◽  
Sang-Youn Bang ◽  
Ki-Won Lee ◽  
Young-Jin Choi ◽  
Yong-Su Kim
Keyword(s):  
High Speed ◽  
Critical Speed ◽  
Structural Integrity ◽  
Normal Operation ◽  
Working Fluid ◽  
Coolant Pump ◽  
Integrity Assessment ◽  
Reactor Coolant ◽  
Pump Shaft ◽  
Accident Conditions

The RCP (Reactor Coolant Pump) is operated in high speed and high pressure conditions. Therefore, the problem of vibration has arisen caused by the hydraulic forces of the working fluid. These forces can drastically alter the critical speeds and stability characteristics, and can act as significant destabilizing forces. In this study, the structural integrity of the pump shaft of APR1400 RCP estimated under normal operation and accident conditions. In order to predict the vibration behavior and dynamic characteristics, modal and critical speed analysis were performed. For evaluation due to the load cases, stress characteristics were investigated. This paper shows that the 1st critical speed occurs at over rotational speed range and the calculation and analysis result of the pump shaft satisfied the code requirement.

The Performance Analysis of a Reactor Coolant Pump Hydro-Static Seal in Different Operating Conditions by Reynolds Equations

2017 ◽  
Author(s):  
Guohui Cong ◽  
Yixun Zhang ◽  
Tiejian Zhang ◽  
Kan Chen
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Nuclear Power ◽  
Leakage Rate ◽  
Operating Conditions ◽  
Shaft Seal ◽  
Coolant Pump ◽  
Reynolds Equations ◽  
Reactor Coolant ◽  
Calculation Results

The reactor coolant pump is the key equipment of the first loop in nuclear power plant, and the shaft seal is the most important component. The reliability of the shaft seal under various operating conditions directly affects the safe operation of the reactor coolant pump and the plant. At present, the large shaft diameter No.1 shaft seal used in the nuclear power plant is mostly in a hydro-static type with single taper. In order to analyze the No. 1 seal performance which is impacted by the pressure, temperature and speed of the reactor coolant pump, the simplified Reynolds equations is used to calculate the fluid domain of No. 1 seal by the numerical method. The analysis obtains the No. 1 seal surface pressure distribution, then the No. 1 sealing film thickness, leakage rate and other performance parameters under different pressure, temperature and speed conditions are analyzed and results obtained. In the analysis, the deformation of the sealing surface influenced by the temperature is not considered, but the high temperature impact under SBO condition is analyzed and predicted. The influence of speed variation with the increase of centrifugal force in the calculation is considered. The results show that the leakage increases with the increase of pressure, and is more sensitive under low pressure. The leakage quantity increases with the increase of temperature, below 100°C, the leakage is basically in near linear change trend, but in the high temperature about 300°C in SBO condition, the leakage rate increases obviously. For the large diameter hydro-static seal, due to the large rotating radius, the circumferential velocity is relatively high; under the action of centrifugal force the leakage rate is lower when the speed is higher. The calculation results of hydro-static pressure under different pressure level are compared with the experimental results, the calculation results of the trend is consistent with the experimental result, and when the pressure becomes larger, the calculation results and the experimental results are more different. The results also show that although the direct use of the Reynolds equation cannot reflect the interaction influence of fluid, solid and heat transfer, but compared with the test results, the trend of the calculation and the test is the same. In conclusion, the calculation method by Reynolds equations can be used in the guide of reactor coolant pumps No.1 seal design, but the design detailed should be corrected by the real test data.

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