Blade Stress of the Reactor Coolant Pump of 300 MWe Nuclear Power Plant in China Based on Fluid-solid Coupling Method

2010 ◽  
Vol 46 (04) ◽  
pp. 111 ◽  
Author(s):  
Xiangyang CHEN
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Coupling Method ◽  
Coolant Pump ◽  
Reactor Coolant

Seismic Response Analysis of Reactor Coolant Pump in Nuclear Power Plant

2008 ◽  
Author(s):  
Zhaohui Ren ◽  
Hui Ma ◽  
He Li ◽  
Guiqiu Song ◽  
Wenjian Zhou
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Structural Design ◽  
Nuclear Power ◽  
Response Spectrum ◽  
Response Analysis ◽  
Response Spectrum Analysis ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Modes Of Vibration

The reactor coolant pump in nuclear power plant is the only revolving equipment in the nuclear power plant. Its functional stability will directly affect the security of nuclear power plant. The coolant pump of a very nuclear plant is examined by using response spectrum analysis to analysis dynamic characteristics and responses aiming at finding the natural frequencies of vibration, modes of vibration and seismic responses, and any possible step which may cause damage of the whole system. The favorable spectrum and unfavorable one are investigated as well. The paper focuses on avoiding the detrimental effects caused by earthquakes, therefore may lay down a theoretical foundation for structural design and installation.

Study and Design of Monitoring System of Reactor Coolant Pump in Nuclear Power Plant

2010 ◽  
Author(s):  
Lei You ◽  
Fuchun Sun ◽  
Pan He ◽  
Hongkun Xu ◽  
Fang Fang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Monitoring System ◽  
Virtual Instrument ◽  
Nuclear Power ◽  
Failure Process ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Instrument Technology ◽  
The Fourier Transform

In this paper, we develop a monitoring system of reactor coolant pumps in nuclear power plant (CPS). The safe running of reactor coolant pump is important for nuclear power plant. Based on the Fourier transform (FT) and some algorithm, The data collected from the pump are analyzed. Once the accident happens, it would cause unimaginable outcome. The system will be jumped to failure process mode when the pump has something wrong. The advanced VXI and virtual instrument technology are applied to system, and the reactor coolant pump will be monitored overall so as to assure that the reactor coolant pump runs in safe, which has a significant value to secure the safe operation and reliability of the nuclear plant. The monitoring system will help the operators find fault of reactor coolant pump.

Application of Joint Boring Technique in Solving RCL Wall Thickness Problem

2017 ◽  
Author(s):  
Huadong Zhu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Wall Thickness ◽  
Nuclear Power ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Design Requirements ◽  
Nuclear Power Project ◽  
Power Project ◽  
Service Inspection

Nuclear Power Project RCL (reactor coolant loop) is one of the most critical nuclear safety class 1 equipment in PWR nuclear power plant. Filled with borated water, the RCL is a closed loop and serves as pressure boundary incorporating the reactor pressure vessel, steam generator and reactor coolant pump. Since in-service inspection is required for welds of the RCL, the two sides of the welds shall be bored to meet UT (Ultrasonic Testing) inspection requirements. The design standard states that “if the weld is subject to service inspection, the length of the counterbore shall be 2Tmin (Tmin = minimum of wall thickness) for pipe and Tmin for components and fittings. Therefore, the minimal wall thickness of the boring area inside the RCL shall also meet design requirements. Examination of the RCLs delivered to the nuclear power project sites showed that the wall thickness of some parts of the RCL exceed tolerance in varying degrees (the wall thickness is too thin). The RCL borings need to be analyzed to mitigate the negative impact of insufficient wall thickness, maintain RCL wall thickness to the largest extent and meet design requirements. Under the condition of the jobsite data are idealized, this study analyzes the boring plans for the cold leg of loop B at the reactor vessel side for this nuclear power plant Unit 1 NI (Nuclear Island) and discusses the three methods of boring, namely, general boring, taper boring and eccentric boring. It finds that a combination of taper boring and eccentric boring is the optimal plan. This joint boring technique can help achieve the minimal boring wall thickness, reduce the grinding quantity and maintain the required wall thickness, thus resolving the out-of-tolerance issue. In addition, it meets the design requirements, the wall thickness and in-service inspection requirements. Supervision agency approved the application of the joint boring technique to the RCL for the projects. The RCL installation has proved to be a success.

Decontamination of the reactor coolant pump in Maanshan nuclear power plant

1996 ◽  
Vol 167 (1) ◽  
pp. 91-97 ◽  
Author(s):  
Iuan-Jou Yang ◽  
Mao-Ying Teng ◽  
Wu-Ing Huan ◽  
Yuan-Lung Sun
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Coolant Pump ◽  
Reactor Coolant

scholarly journals Extended station blackout analyses of an APR1400 with MARS-KS

2016 ◽  
Vol 31 (4) ◽  
pp. 318-326
Author(s):  
Woongbae Kim ◽  
Hyungwook Jang ◽  
Seungjong Oh ◽  
Sangyong Lee
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Electric Energy ◽  
Computer Code ◽  
Sensitivity Study ◽  
Battery Life ◽  
Coolant Pump ◽  
Reactor Coolant ◽  
Station Blackout

The Fukushima Daiichi nuclear power plant accident shows that natural disasters such as earthquakes and the subsequent tsunamis can cause station blackout for several days. The electric energy required for essential systems during a station blackout is provided from emergency backup batteries installed at the nuclear power plant. In South Korea, in the event of an extended station blackout, the life of these emergency backup batteries has recently been extended from 8 hours to 24 hours at Shin-Kori 5, 6, and APR1400 for design certification. For a battery life of 24 hours, available safety means system, equipment and procedures are studied and analyzed in their ability to cope with an extended station blackout. A sensitivity study of reactor coolant pump seal leakage is performed to verify how different seal leakages could affect the system. For simulating extended station blackout scenarios, the best estimate MARS-KS computer code was used. In this paper, an APR1400 RELAP5 input deck was developed for station blackout scenario to analyze operation strategy by manually depressurizing the reactor coolant system through the steam generator's secondary side. Additionally, a sensitivity study on reactor coolant pump seal leakage was carried out.

A High Effective Parallel Method for the Coupling Between Neutronics and Thermal-Hydraulic

2016 ◽  
Author(s):  
Xiaomeng Dong ◽  
Zhijian Zhang ◽  
Zhaofei Tian ◽  
Lei Li ◽  
Guangliang Chen
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Large Scale ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Decisive Role ◽  
Reactor Power ◽  
Coupling Method ◽  
Outlet Temperature

Multi-physics coupling analysis is one of the most important fields among the analysis of nuclear power plant. The basis of multi-physics coupling is the coupling between neutronics and thermal-hydraulic because it plays a decisive role in the computation of reactor power, outlet temperature of the reactor core and pressure of vessel, which determines the economy and security of the nuclear power plant. This paper develops a coupling method which uses OPENFOAM and the REMARK code. OPENFOAM is a 3-dimension CFD open-source code for thermal-hydraulic, and the REMARK code (produced by GSE Systems) is a real-time simulation multi-group core model for neutronics while it solves diffusion equations. Additionally, a coupled computation using these two codes is new and has not been done. The method is tested and verified using data of the QINSHAN Phase II typical nuclear reactor which will have 16 × 121 elements. The coupled code has been modified to adapt unlimited CPUs after parallelization. With the further development and additional testing, this coupling method has the potential to extend to a more large-scale and accurate computation.

Steam Generator Modal Analysis of Nuclear Power Plant

2017 ◽  
Author(s):  
Lu Yan ◽  
Chu Qibao ◽  
Wang Qing ◽  
Fang Yonggang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Modal Analysis ◽  
Steam Generator ◽  
Nuclear Power ◽  
Simplified Model ◽  
Loop Analysis ◽  
Reactor Coolant ◽  
Coolant Loop ◽  
Design Correctness

A method for forming a simplified model of steam generator which will be used in reactor coolant loop analysis has been shown here, as well as the modal analysis to this simplified SG model. This modal analysis results and the results of the SG provided by NPP designer are compared together in order to prove the design correctness. The comparison shows that the two are basically consistent.

Vibration Alarm Analysis and Treatment of Main Coolant Pump in Nuclear Power Plant

2017 ◽  
Author(s):  
Zhen Li ◽  
Pengcheng Du ◽  
Gujian Ma
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Water Flow ◽  
Vibration Analysis ◽  
Nuclear Power ◽  
Dynamic Balance ◽  
Coolant Pump ◽  
Pump Design ◽  
Pump Shaft ◽  
Shaft Vibration

The structure of main coolant pump in a nuclear power plant and vibration alarm are introduced. Vibration analysis and trouble diagnosis have been carried out. It shows that pump shaft vibration is mainly composed of running frequency (1×) and half of running frequency (0.5×), motor shaft vibration is just composed of 1×. The vibration fluctuation in pump shaft is caused by the variation of amplitude in 0.5×. Based on vibration analysis result, the fault investigation has been launched, in which it includes installment, measurement, dynamic balance and pump design. After detailed investigation, the excessive vibration was induced by the dynamic unbalance of pump shaft and unsteady vortex of shaft seal water. The research for treatment has been implemented on dynamic balance and seal water flow. It is suggested to increase the seal water flow to control vibration fluctuation. The result shows that this method is effective, economical, safe, and very easy to implement for suppressing flash vibration alarm.

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