scholarly journals Leak Detection in the Primary Reactor Coolant Piping of Nuclear Power Plant by Applying Beam-Microphone Technology

2004 ◽  
Vol 41 (3) ◽  
pp. 359-366 ◽  
Author(s):  
Yoshimitsu KASAI ◽  
Sergey SHIMANSKIY ◽  
Yosuke NAOI ◽  
Junichi KANAZAWA
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Leak Detection ◽  
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.

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.

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.

Design Characteristics of Ulchin Nuclear Power Units 5&6

2002 ◽  
Author(s):  
Deucksoo Lee ◽  
Dong-Su Kim ◽  
Young-Taik Lee ◽  
O-Keol Kwon ◽  
Jung-Cha Kim
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
System Design ◽  
Nuclear Power ◽  
Safety Analysis ◽  
Reactor Coolant ◽  
The Core ◽  
Core Damage ◽  
Actuation System ◽  
Design Characteristics

Ulchin nuclear power plant units 5&6 (UCN 5&6), which started excavation on January 1999, are two loop pressurized water reactors (PWR) with the capacity of 1000 MWe, and planned to start commercial operation on June, 2004 and June, 2005, respectively. The reactor coolant system of the UCN 5&6 consist of a reactor vessel, internals, and two steam generators, four reactor coolant pumps, a pressurizer and primary piping. Based on the system design of the first Korean Standard Nuclear Power Plant (KSNP), UCN 5&6 is designed to provide improvements in safety, reliability and cost by applying both advanced proven technology and experiences gained from the construction and operation of the previous KSNP plants. The result of the preliminary probabilistic safety assessment study for UCN 5&6 shows that the core damage frequency is lowered significantly. Several design improvement items have been adopted to the system design and contributed to lower the core damage frequency value. Among the design improvements, digital PPS and digital ESFAS are the key to the UCN 5&6 design. Furthermore, digitization of the Plant Protection System (PPS) and Engineered Safety Feature Actuation System (ESFAS) for the PWR is the first case in the PWR construction history. The Korean regulatory body reviewed the design concept of the digital PPS and digital ESFAS, and evaluated to be acceptable for the plant safety. Also, in-depth review on the detail design of the digital PPS/ESFAS and the special evaluation/audit for the software design process are underway to secure the software quality. The safety of the UCN 5&6 design has been evaluated through a two-year review on the preliminary safety analysis report. As a result, the construction permit was issued on May 17, 1999 by the government. In this paper, design characteristics of UCN 5&6 are discussed focussed on design improvements comparing with KSNR. And, some of the safety analysis results are presented as well as licensing status.

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