Method for Measuring Temperature of Inner Wall Surface of Pipeline in Nuclear Power Plant

2017 ◽  
Author(s):  
Ling Jun ◽  
Wang Hai-jun ◽  
Liu Lang ◽  
Chen Tong ◽  
Liu Hong-tao ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Thermal Fatigue ◽  
Nuclear Power ◽  
Control Method ◽  
Temperature Fluctuations ◽  
Mathematic Model ◽  
Volume Control ◽  
Pipe System ◽  
Prime Problem

Thermal stratification can occur when hot and cold fluids mix inside the pipeline of nuclear power plant, which can lead to temperature fluctuations with large amplitude and high frequency with time-varying wall heat stress and even induce thermal fatigue phenomenon. Therefore, how to accurately get temperature fluctuations of the inner wall without damaging the whole structure of the pipe system becomes the prime problem to be solved in the study of thermal fatigue. Base on energy conservation law, the non-iterative mathematic model of inverse heat conduction using the volume-control method has been developed in this paper for pipe in nuclear power plant. Numerical and experiment results show that the volume-control method can accurately catch the temperature fluctuation of different positions on the inner wall.

Study on Sensor with Mechanical Properties in Nuclear Power Plant with Application of BP Neural Network to Fault Tolerant Control

2013 ◽  
Vol 644 ◽  
pp. 56-59
Author(s):  
Jin Yang Li ◽  
Hong Xia ◽  
Shou Yu Cheng
Keyword(s):  
Neural Network ◽  
Mechanical Properties ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Bp Neural Network ◽  
Nuclear Power ◽  
Control Method ◽  
Fault Tolerant ◽  
Fault Tolerant Control ◽  
Level Sensor

All kinds of sensor with mechanical properties often can go wrong in nuclear power plant. In this kind of situation, it puts forward a kind of active fault tolerant control method based on the improved BP neural network. Firstly, the method will train sensor by BP neural network. Secondly, it will be established dynamic model bank in all kinds of running state. The system will be detected by using BP neural network real time. When the sensor goes wrong, it will be controled by reconstruction. Taking pressurizer water-level sensor as the case, a simulation experiment was performed on the nuclear power plant simulator. The results showed that the proposed method is valid for the fault tolerant control of sensor in nuclear power plant.

Verification of Accumulator Model in COSINE

2013 ◽  
Author(s):  
Huie Sha ◽  
Hao Zhang ◽  
Zheng Du ◽  
Yiqiang Xiong ◽  
Yanhua Yang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Liquid Flow ◽  
Nuclear Power ◽  
Mathematic Model ◽  
Wall Friction ◽  
Plant Design ◽  
Software Platform ◽  
Gravity Effects ◽  
Isothermal System

The objective of COSINE (COre and System INtegrated Engine for design and analysis) project is to develop a software platform which is used for nuclear power plant design and safety analysis. The system code (SYST) is a part of COSINE code. In this paper, the mathematic model of accumulator is established. The model is based on following assumptions: nitrogen above liquid level in accumulator is represented in idea gas equation, water is modeled as an isothermal system. The model for liquid flow include inertia, wall friction, form loss, and gravity effects. Several cases were calculated under different conditions, and the results were compared with RELAP5. It shows that COSINE results agree well with RELAP5.

Overview on the Design Approach for the CVCS I & C of the EPR™ Nuclear Power Plant in Taishan

2013 ◽  
Author(s):  
Antonio Ciriello ◽  
Daniela Kohler ◽  
Terry Morton ◽  
Thomas Lang
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Engineering Design ◽  
Nuclear Power ◽  
Control Design ◽  
Volume Control ◽  
Functional Safety ◽  
Control Loop ◽  
And Control

The I & C (Instrumentation and Control) design of the CVCS (Chemical and Volume Control System) for the EPR™ nuclear power plant in Taishan (TSN NPP) is shortly introduced and the corresponding I & C module assignment procedure, according to the functional safety class principle, is described. An example of the I & C module assignment procedure is given for a control loop of the CVCS. In addition, the corresponding advantages and drawbacks are described and discussed. The approach described introduces a new method for the concerned I & C design by improving the interface between the system, process, and I & C engineering design. In fact, a fruitful collaboration was reached between the system and I & C design for the EPR™ project in Taishan, for the concerned interface.

Study on the Quality Control Method of Nuclear Power Plant Project

2015 ◽  
Vol 1092-1093 ◽  
pp. 459-462
Author(s):  
Feng Ling Zheng
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Control Method ◽  
Paper Analysis ◽  
Production Cycle ◽  
Construction Quality ◽  
Project Construction ◽  
Set Up

Nuclear power plant engineering quality is the security of nuclear safety. The main danger source of nuclear power plants is the nuclear island. Once the project quality uncontrollable, radioactive nuclear fuel could be harm to human and environmental in the nuclear power station trial operation or production cycle. So this paper analysis the effect factors of the nuclear power construction quality, and concludes it must to be control strictly the project construction quality of the nuclear power plant, and use the prevention and control method to set up quality defensive barrier to eliminate the problems of engineering quality.

Methods of detailed thermal fatigue evaluation of nuclear power plant components

2011 ◽  
Vol 42 (12) ◽  
pp. 1082-1092 ◽  
Author(s):  
J. Rudolph ◽  
S. Bergholz ◽  
A. Willuweit ◽  
M. Vormwald ◽  
K. Bauerbach
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Thermal Fatigue ◽  
Nuclear Power ◽  
Fatigue Evaluation ◽  
Plant Components

Research on Pressurizer Pressure Control System of 900MW Pressurized Water Reactor Nuclear Power Plant

2013 ◽  
Vol 718-720 ◽  
pp. 1215-1220
Author(s):  
Guo Duo Zhang ◽  
Xu Hong Yang ◽  
Si Yu Qiao ◽  
Yu Jun Wu
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Control Method ◽  
Pressure Control ◽  
Sharp Change ◽  
Control Technology ◽  
Pressurized Water ◽  
Pressure Control System

It is of vital importance for the pressurizer to maintain the pressure of primary coolant because the sharp change of coolant pressure has a direct impact on the security of reactor. The study of pressurizers pressure control method is highly important and meaningful. This paper presents the researching and designing on pressure control system of a pressurizer implemented in a nuclear power plant. Both the present situation of the nuclear power and some relevant background have been briefly introduced. Proceeding on the records of simulation, we succeed in establishing the applied modeling of pressurizer and further propose the PID control technology working as control algorithm. The best set of controller parameters are chosen through comparing the results including regulation time, overshoot suppression and stability. On the base of such control method, we attempt to add neural network control technology to achieve further improvement, which turns out available and satisfying.

Isogeometric Analysis of Pipe System in Nuclear Power Plant

2017 ◽  
Author(s):  
Le Shen ◽  
Yang Xia
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Isogeometric Analysis ◽  
Computer Aided Design ◽  
Nuclear Power ◽  
Great Accuracy ◽  
Pipeline System ◽  
Pipe System ◽  
Displacement Boundary ◽  
Geometry Model

The security of pipe system is an important problem in nuclear power plant. The displacement field and vibration frequency of the pipeline system under given loads and displacement boundary conditions are calculated with isogeometric analysis. Comparisons with commercial softwares are given to prove its effectiveness. In isogeometric analysis the non-uniform rational B-spline (NURBS) basis functions are used to accurately describe the geometry of pipeline, which can be imported directly from the geometry model designed by computer aided design (CAD) tools for numerical analysis. The quarter bend pipes are described precisely with only limited control points and the approximation by straight line elements in finite element method based simulation is replaced. Present simulation with isogeometric analysis can simplify the modelling process of pipeline system and improve the efficiency of the simulation with great accuracy.

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