Study on control system and control strategies of natural circulation and forced circulation in Nuclear Power Plant

2010 ◽  
Author(s):  
Shou-yu Cheng ◽  
Min-jun Peng ◽  
Cheng Gong ◽  
Zhao-Fei Tian ◽  
Qiang Zhao ◽  
...  
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Control Strategies ◽  
Natural Circulation ◽  
Forced Circulation ◽  
And Control

Design and Function Realization of Nuclear Power Inspection Robot System

Robotica ◽  
2020 ◽  
Vol 39 (1) ◽  
pp. 165-180
Author(s):  
Zhang Zhonglin ◽  
Fu Bin ◽  
Li Liquan ◽  
Yang Encheng
Keyword(s):  
Control System ◽  
Remote Control ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Pid Control ◽  
Nuclear Power ◽  
Control Operation ◽  
Inspection Robot ◽  
Walking Mechanism ◽  
And Control

SUMMARYThe particularity of nuclear power plant environment requires that the nuclear power inspection robot must be remote control operation. The main purpose of the inspection robot is to carry out inspection, prevention, reporting, and safety emergency operation on the instruments, so as to provide guarantee for the safe operation of the nuclear power plant. Based on the representative configuration of nuclear power robot at home and abroad, this paper develops a small and lightweight nuclear power plant inspection robot, including walking mechanism, lifting mechanism, operating mechanism, image acquisition, information communication and control system, etc., to carry on the statics analysis to the key components of the inspection robot and verify that the stiffness and strength of the mechanical structure meet the requirements of lightweight design. Modal analysis is carried out to verify that the motor does not cause resonance when working. The kinematic model of the robot has been established and can provide the theoretical basis for the controller design. A hierarchical control system based on LabVIEW upper computer monitoring and control operation interface is established, which uses adaptive fuzzy Proportional Integral Derivative (PID) control to simulate the walking control, and then realizes the control of walking mechanism through software programming, and the adaptive fuzzy PID control has better effect than the conventional PID control. The S-type acceleration and deceleration algorithm is used to realize the accurate control of the position location of the lifting mechanism. Finally, combined with the experiment of 5MS robot comprehensive experimental platform, it is proved that the inspection robot can realize remote control function operation.

Modeling uncertainty of instrument and control system of nuclear power plant

2020 ◽  
Vol 139 ◽  
pp. 107207
Author(s):  
Raj kamal Kaur ◽  
Lalit Kumar Singh ◽  
Aditya Khamparia
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Modeling Uncertainty ◽  
And Control

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.

Effects of Rolling on Characteristics of System Under Forced Circulation and Natural Circulation

2020 ◽  
Author(s):  
Rong Cai ◽  
Nina Yue ◽  
Hongyu Fang ◽  
Baowen Chen ◽  
Lili Liu ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Natural Circulation ◽  
Thermal Parameters ◽  
Reactor System ◽  
Hydraulic Characteristics ◽  
Forced Circulation ◽  
Rolling Condition

Abstract The marine nuclear power plant operating in the marine environment has complicated motion under the influence of wind and waves. The movement of marine nuclear power plant will affect the thermal-hydraulic characteristics of its nuclear reactor system. Compared with other typical motion conditions, the effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system are the most complex. In order to study the effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system, a thermal-hydraulic system code for motion conditions named STAC was developed. The STAC code was verified by the experiments conducted in Japan. The effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system under forced circulation and natural circulation are studied with the STAC code. The simulation results show that the thermal parameters of the reactor system under rolling condition fluctuate periodically. The fluctuation period of the thermal parameters of the core is half of the rolling period, and the fluctuation periods of other thermal parameters are the same as the rolling period. The effect of rolling condition on thermal-hydraulic parameters under forced circulation is smaller than that under natural circulation. The fluctuation amplitudes of the thermal parameters increase with the angle amplitude of the rolling condition. There is a rolling period with the smallest fluctuation amplitude. Under the rolling condition with short period, the fluctuation amplitudes of the thermal parameters increase and their average values change rapidly as the rolling period decreases. Under the rolling condition with large period, the fluctuation amplitudes of the thermal parameters increase with the rolling period, and they tend to fixed values.

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